vvEPA
United Statei
Envtronmantal Protection
Agoncy
Office ?f
Radiation Progratm
Washington DC 204SO
Jansjary 1983
Radiation
Potential Individual
Doses from Disposal
of High-level Radioactive
Wastes In Geologic
Repositories
Draft Report
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TECHNICAL REPORT DATA
(Please read Instructions on the reverse before completing)
.REPORT NO.
520/1-82-026
3. RECIPIENT'S ACCESSION N,O.
3
4. TITLi AND SUBTITLE
5. REPORT DA;
Potential Individual Doses from Disposal of High-level
Radioactive Wastes In Geologic Repositories
1182
6. PERFORMING ORGANIZATION COOi
AUTHORIS!
Abraham S. Go!din
Cheng-Yeng Hun C,
Barry L. Serini
Bruce Smith
Richard K, Struckme
8. PERFORMING ORGANIZATION REPORT NO.
/er
9. PERFORMING ORGANIZATION NAME AND ADDRESS
10. PROGRAM ELEMENT NO.
11. CONTRACT/GRANT NO.
12. SPONSORING AGENCY NAME AND ADDRESS
Environmental Protection Agency
•.401.-fl Street, -S.W..-- -. •
Washington, D.C. 20460
13. TYPE OP REPORT AND PERIOD COVERED
Draft/Final
14. SPONSORING AGENCY CODE
200/03
IS. SUPPLEMENTARY NOTES
16. ABSTRACT ,^~.-~~-
The-".0incy has recently published environmetnal standards addressing disposal of high
level!radioactive wastes (40 CFR Part 191) for public review and comment {47 FR 58196).
An important part of this effort is the evaluation of how effective mined geologic
repositories are for isolating these wastes from the environment for many thousands
of years.. EPA's assessments indicate that carefully designed repositories at good
sites can, keep long-term risks below those that would exist if (on a generic basis)
the uranium ore used to create the wastes had not been mined initially. Accordingly,
the Agency has proposed environmental standards that would restrict projected releases
fjrom high-level waste disposal systems—for 10,000 years after disposal to levels
\ that should keep the risks to future generations less than those to which they would
,.\jhave been exposed from the unmined ore if these wastes had not been created.
"This technical report presents the methodology used to assess the potential annual
individual doses and human exposure and geologic media contamination probabilities
from projected releases of radioisotopes from a geologic repository. It describes
the models that the*-Agency employed for this analysis and reviews the various assumptio
which were made. Since this analysis is necessarily generic in nature, the methodology
uses very general models of environmental pathways and considers a range of values
for the various parameters used in the models.
is
17.
KEY WORDS AND DOCUMENT ANALYSIS
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unlimited
! 19. SECURITY CLASS (ThisReport/
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21. NO. OF PAGES
215
;20. SECURITY CLASS ffllispegs)
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22. PRICE
EPA Form 2220-1 (Rev. 4-77) PREVIOUS EDITION is OBSOLETE
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EPA520/1-82-026
Potential Individual Doses from Disposal
of High-Level Radioactive Wastes
In Geologic Repositories
Draft Report
January 1983
Abraham S. Goldin
Barry L. Serini
Richard K. Struckmeyer
Cheng-Yeng Hung
C. Bruce Smith
Office of Radiation Programs
U.S. Environmental Protection Agency
Washington, D.C. 20460
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FOREWORD
The Agency has recently published environmental standards
addressing disposal of high-level radioactive wastes (40 CFR Part 191)
for public review and comment (47 FR 58196). An important part of this
effort is the' evaluation of how effective mined geologic repositories
are for isolating these wastes from the environment for many thousands
of years. EPA's assessments indicate that carefully designed
repositories at good sites can keep long-term risks below those that
would exist if (on a generic basis) the uranium ore used to create the
wastes had not been mined initially. Accordingly, the Agency has pro-
posed environmental standards that would restrict projected releases
from high-level waste disposal systems—for 10,000 years after disposal
—to levels that should keep the risks to future generations less than
those to which they would have been exposed from the unmined ore if
these wastes had not been created.
This technical report presents the methodology used to assess the
potential annual individual doses and human exposure and geologic media
contamination probabilities from projected releases of radioisotopes
from a geologic repository. It describes the models that the Agency
employed for this analysis and reviews the various assumptions which
were made. Since this analysis is necessarily generic in nature, the
methodology uses very general models of environmental pathways and
considers a range of values for the various parameters used in the
models.
Because much of this methodology is new, the Agency is publishing
this report in draft form. During the public comment period regarding
40 CFR 191, a Subcommittee of the Agency's Science Advisory Board will
conduct an independent technical review of our risk assessments
(48 FR 509). All meetings of this Subcommittee will be announced in
the Federal Register and will be open to the public.
In addition, I encourage users of this report to submit any
cements or suggestions they might have. Such comments would be most
helpful if received by May 2, 1983. They should be sent to: Central
Docket Section (A-130); Attn: Docket No. R-82-3; Environmental
Protection Agency; Washington, D.C. 20460.
Glen L^Sjoblom
Director
Office of Radiation Programs
n
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Table of Contents
Chapter 1: Summary 1
1.1 Introduction 1
1.2 Nuclide Releases 1
1.3 Nuclide Transport 2
1.4 Annual Dose Rates and Contaminated Areas 4
1.5 Results of Varying System Characteristics 6
Chapter 2; Introduction 9
2.1 Purpose of the Report 9
2.2 Plan of the Report 10
Chapter 3: Description of the Model 13
3.1 Introduction 13
3.2 The Disposal System 13
3.2.1 The repositories 13
3.2.2 The wastes 14
3,2.3 The environment 19
3.3 Initiating Events and Release Modes 20
3.4 Release Scenarios 23
3.4.1 Drilling for resources 23
3,4.2 Faulting 26
3.5 Dosimetry 27
3.5.1 Choice of organs 28
3.5.2 Annual dose rates from drinking water 29
3.5.3 Annual dose rates from inhalation 29
3.6 Method of Calculating Dose 31
3.7 Event Times 32
3.8 Kisk and Probability 32
3.8.1 Probability of contamination 33
3.8.2 Probability of exposure 33
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Cnapter 4: Release and Transport of Radionuclides 37
4.1 Release to the Aquifer due to Drilling 37
4.1.1 Release rate from the repository 38
4.1.2 Transport in the aquifer 43
4.1.3 Concentration in the aquifer due to drilling 47
4.2 Release to the Aquifer due to Faulting 50
4.2.1 Leaching governs release 51
4.2.2 Radionuclide solubility governs release 53
4.2.3 Uranium oxide solubility governs release 53
4.2.4 Fault disturbs the granite tank 54
4.3 Release to the Land Surface 54
4.3.1 Direct drilling hit on waste 58
4.3.2 Liquid from a brine pocket or granite tank 58
Chapter 5: Results of the Reference Disposal System Analysis 61
5.1 Release to the Aquifer due to Drilling 63
5.1.1 Direct hit on waste 69
5.1.2 Brine pocket 75
5.1.3 Sranite tank - 77
5.2 Release to the Aquifer due to Faulting 88
5.2.1 Fault hits waste 88
5.2.2 Faulting through a granite tank or brine pocket 91
5.3. Release to the Land Surface 95
5.3.1 Direct hit on waste 95
5.3.2 Brine pocket 100
5.3.3 Granite tank 109
5.4 Release to the Aquifer due to Shaft Seal Leakage 113
Chapter 6: Results of the SensitivityAnalysis 119
6.1 Effect of Varying Canister Life 119
6.1.1 Release to the aquifer due to drilling 120
6.1.2 Release to the aquifer due to faulting 121
6.1.3 Release to the land surface 121
6.2 Effect of No Solubility Limits 130
6.2.1 Release to the aquifer due to drilling 130
6.2.2 Release to the aquifer due to faulting 135
6.2.3 Release to the land surface 138
6.2.4 Release to the aquifer due to shaft seal leakage 138
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6.3 Effect of Varying the Leach Rate 138
6.3.1 Release to the aquifer due to drilling 142
6.3.2 Release to the aquifer due to faulting 157
6.3.3 Release to the land surface 161
6.4 Effect of Varying the Retardation Factors 168
6.4.1 All retardation factors equal one 172
6.4.2 Higher retardation factors 182
6.5 Effect of a Better-Sealed Borehole 182
6.5.1 Direct hit on waste 188
6.5.2 Granite tank 188
6.5.3 Brine pocket 191
6.6 Effect of Varying the Sroundwater Velocity 191
6.6.1 Release to the aquifer due to drilling 194
6.6.2 Release to the aquifer due to faulting 200
6.7 Summary 212
References 215
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Chapter 1
Summary
1.1 Introduction
This report presents potential annual,dose equivalents (hereafter
called doses or dose rates) to individuals exposed to radionuclides
released from a high-level waste repository to groundwater (aquifers)
or to the earth's surface. The modeled repository is filled with spent
reactor fuel elements that have been packaged in canisters. The
repository is deep below the earth's surface. Four shafts needed in
building and filling the repository have been resealed. In this
report, we consider repositories placed in bedded salt and granite, and
provide separate results for releases from repositories in each host
medium. The salt repository has an overlying and an underlying
aquifer; the granite repository has only an overlying aquifer.
Nuclides can be released from the repositories to man's environment as
a result of direct removal of the waste to the surface, direct contact
between the waste and groundwater and subsequent transport to an
aquifer, or release of wafcer from a region of contaminated porous
backfill to the surface. The backfill water becomes contaminated after
failure of the canisters by corrosion. The region of contaminated
backfill in a granite repository is called the "granite tank";
contaminated water in a salt repository is contained in "brine pockets."
1.2 Nuclide Releases
We examined seven ways in which nuclides can be released from a
deep mined geologic repository into the bioshpere. The first four
types of release are caused by someone drilling into the repository in
search of resources: 1) the drill hits radioactive waste and brings it
to the land surface; 2) the drill hits waste and releases radionuclides
to the aquifer; 3) the drill does not hit waste directly, but enters a
brine pocket or granite tank, releasing radionuclides to the land
surface; 4) the drill intersects the tank or brine pocket, releasing
radionuclides to the aquifer.
4
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Events five and six involve fault movement in the area of the
repository: 5} the fault directly hits waste in a row of canisters,
releasing nuclides to the aquifer; 6) the fault disrupts the tank or
brine pocket, and radionuclides are released to the aquifer. And
finally, 7} radionuclides are released from the repository to the
aquifer because of shaft seal leakage.
We selected drilling for consideration because it would release
more waste than leakage through a resealed borehole would, and because
it would produce a more concentrated release than flow through bulk
rock. We selected faulting because it would release more waste than a
breccia pipe would. We omitted releases from volcanic action, igneous
intrusions, and meteorite impacts, as too improbable to serve as a
basis for regulation.
1.3 Nuclide Transport
For a release to the land surface, we calculated annual dose rates
to the lungs from inhaling contaminated air near the drilling site.
Our model assumes that when a person drills into the repository and
hits the waste, 15% percent of the waste from one canister, in its
original insoluble form, will be carried to the surface by the drill
bit. Once the waste is deposited on the land surface, a portion of the
nuclides will disperse into the air. We assume average dispersion
conditions, and we assume the wastes disperse radially from the point
source. The nuclides will eventually be removed from the land surface
by radioactive decay and infiltration into the soil.
Nuclides released to the land surface by drilling into contaminated
repository water are in a soluble chemical form. The amount of material
released is different from that released by a direct hit on waste. For
example, the granite tank inventory of americium (Am)-2fll, the most
harmful nuclide in the inhalation pathway, increases for about 1200 years.
However, as nuclides leach out of the waste matrix and into the tank,
they are decaying. Eventually, the inventory in the tank declines
because of radioactive decay. Drilling into granite removes 200 cubic
•)
meters (m ), or 0.01%, of the contaminated water. The nuclide
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content of this water is smaller than that which would be released by a
direct hit on waste, and consequently doses are smaller. Drilling into
a brine pocket (0.06 m ) releases an even smaller quantity of
contaminated water and the doses are very small.
We calculated the effects of both the leach rates of the waste
matrix and the solubilities of the nuclides as they affect the entrance
of the nuclides into the aquifer. Leach rate refers to the rate at
which the waste matrix in contact with groundwater dagrades and allows
nuclides to filter into the groia.dwater. For many nuclides, the leach
rate is the limiting factor controlling their rate of entry into the
aquifer (leach-limited nuclides). For some other nuclides, the rate of
entry into the aquifer is further limited by their low solubility in
groundwater (solubility-limited nuclides).
We studied three drilling releases to aquifers: a direct hit into
the waste, penetration into a brine pocket, and penetration into a
granite tank,. We assume the drill produces a borehole down through the
repository and into any lower aquifer, and that nuclides can flow
through the borehole into the upper aquifer. Transport within the
aquifer is the same in all three cases, but the rates at which the
nuclides enter the aquifer differ in each case. For a direct hit on
waste, the rate of entry into the aquifer of those nuclides that are
leach-limited is the product of the leach rate and the nuclide
inventory in the affected waste. This inventory is reduced by
radioactive decay beginning when the repository is sealed and also by
depletion by leaching removal beginning at the time of drilling. The
rate of entry of solubility-limited nuclides is equal to the water flow
rate through the repository times the solubility. The rate of entry of
nuclides into the aquifer from a brine pocket or granite tank initially
increases as the nuclides leave the waste matrix and enter the tank or
pocket. Eventually, however, the rate of entry Into the aquifer
decreases as the nuclides in the tank or pocket decay.
Two faulting scenarios assuming nuclide transport to an overlying
aquifer were developed. One assumed that the waste was still lined up
in its canisters while the other assumed that nuclides had leached into
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the repository water. After the fault broke open the canisters, we
treated the row of waste as a line source, and summed the effect by
integrating in the fault line from the upstream boundary of the
repository to the downstream boundary. Upstream and downstream refer
to the direction of flow in the upper aquifer. Faulting also disturbs
the contaminated water in the repository. The concentrations and doses
from faulting are the highest found in the study, in part because fault
movement affects the largest fraction of the repository. Chapter 4
presents a detailed mathematical discussion of all the releases covered
in this report.
1.4 Annual Dose Rates and Contaminated Areas
Chapter_5 presents the results of the dose calculations for the
reference repositories. We present here only the annual dose rates
from events occurring 1000 years after the repository is sealed. For
drilling, we calculated the annual dose rates at selected times (dose
times) after the 1000-year event and at pre-selected distances from the
borehole.
A drill that hits the solid waste brings 15% of the waste from one
canister to the surface. The largest annual dose rate is incurred by
breathing contaminated air close to the drilling site (20 meters) ten
years after the event. The dose rate is about eleven rem per year
(rem/yr) to lungs, mostly from Am-241. At longer times after the
drilling, plutonium (Pu)-239 and -240 become dominant, as dose rates
fall from about 4 rem/yr at 1000 years after the event to less than
20 millirem per year at 10,000 years. About ten hectares are contam-
inated enough to give more than 0.5 rem/yr for the first 100 years. As
the nuclides decay, these areas drop to zero after 2000 years.
The same direct hit drilling event will also cause nuclides to be
released to the aquifer. The largest dose rate from drinking contam-
inated aquifer water is about 600 rem/yr to the red bone marrow, again
from Am-241, at 1000 years after the event and 20 meters from the
initial point of release. No areas are contaminated enough to give
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more than 0.5 rem/yr until 1000 years after the event, when Am-241 has
traveled the 20-meter distance and contaminated 0.33 hectares to this
extent. Contaminated areas then increase as the nuclides spread, and
eventually decrease because of radioactive decay. We did not calculate
dose rates from water at distances less than 20 meters because they
would not be representative of the water produced by a well at such
distances. A well brings in water from a considerable extent of the
aquifer, and only a small part of the aquifer would be contaminated
close to the borehole because of very limited transverse spread of
nuclides.
Drilling releases from the brine pocket are different than
releases from the granite tank. The releases to the land surface from
a brine pocket feature Am-241 and -243 as the dominant nuclides, but
the maximum dose rate, 20 meters away and 10 years after the event, is
only 0.02 rem/yr. Land areas contaminated by releases from the granite
tank to give more than 0.5 rem/yr are very small, and by 200 years they
are zero.
Drilling releases to the aquifer from the granite tank and brine
pocket are also modeled differently. The volume of the brine pocket is
0.06 cubic meters (m , about 16 gallons), so the concentration of
americium isotopes is limited by their solubility. The peak dose rate
occurs at 20 meters and 1000 years after the event, and is about
1200 rem/yr, mostly from Am-241. The annual dose rates drop as time
passes and nuclides decay. The model calculations do not show any
areas contaminated enough 10 give more than 0.5 rem/yr until the
americium isotopes have traveled 20 meters, which takes 1000 years.
4. ?
Then, about 0.35 hectares (1 hectare = 10 m } are contaminated
enough to give more than 0.5 rem/yr; this increases to 6.8 hectares
(ha) at 10,000 years. The granite repository dose rates follow the
same course. The highest dose rate in granite, also from Am-241 and
-243, is about 1800 rem/yr. The areas contaminated are slightly
larger, 0.4 ha to give more than 0.5 rem/yr at 1000 years. The
contaminated area reaches its maximum of 7.8 ha at 10B000 years.
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Fault movement affects either a row of waste canisters, brine
pockets, or the granite tank and produces a direct pathway to the
aquifer. The faulting event that hits waste directly produces a
maximum dose rate of 600 rem/yr, 95% from Am-241. The highest dose
rate occurs 500 years after the faulting, and is the same at all
locations along the aquifer above the repository. As the Am-241
decays, Am-243 becomes dominant 5000 years after the event. Releases
from the granite tank caused by fault movement result in a maximum dose
rate of 340,000 rem/yr, 100 years after the event. This is the highest
release and annual dose rate in the base case.
Releases from shaft seal leakage occur only in a granite
repository. They begin when the canisters fail 500 years after the
repository is sealed. The model is the same as for drilling into a
granite tank, but the cross-sectional area of the shaft is used instead
2 2
of that of the borehole, (25.0 square meters (m ) vs. 0.1 m ); and
the initial permeability is 10,000 times lower. These two factors
combine to give somewhat lower flow and lower doses. The maximum dose
rate is 1300 rem/yr, 95X from Am-241. About 0.35 hectares are
contaminated enough to give more than 0,5 rem/yr, compared to 0.36 hect-
ares for the granite tank drilling case.
1.5 Results of Varying System Characteristics
Chapter 5 presents the results of varying model parameters to
determine the sensitivity of our model to input changes. Four of the
six modified input parameters affect the rate of release of the nu-
clides from the repository. They are: 1) the canister life; 2) the
borehole permeability; 3} the leach rate of the waste matrix; and 4)
the solubility limits of the nuclides.
We .examined canister lives of zero and 1000 years. They affect
the rate of release from granite tanks and brine pockets only in those
scenarios where the canisters are not destroyed. The longer the can-
ister life, the lower the dose and the smaller the areas contaminated;
the differences, however, are relatively small.
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p
In the sensitivity analysis, the leach rate was varied from 10
per year (yr )to 10 yr . Higher leach rates give higher
initial doses, but then decrease more rapidly because the amount of
waste available for further entry into the aquifer is rapidly depleted
by leaching. At very high leach rates, the nuclides are depleted so
rapialy that a relatively narrow Dand of contamination passes through
the aquifer.
Nuclide solubility limits the rate at which several elements,
notably the transuranic isotopes, leave the repository and enter the
water.. Because the solubilities of these elements are low in the base
case, the rate at which they leave the repository is lower than the
rate that would be calculated on the basis of leach rates. If we apply
no solubility limits, and use only leach rates in the calculation, the
Plutonium isotopes dominate doses in the later years, with the result
that large areas are contaminated for a long time, and the long term
risk to an individual is greatly increased.
The last two parameters varied were environmental transport
factors, the groundwater velocity and the retardation factor of the
aquifer. The groundwater velocity affects the doses by transporting
the nuclides to a given point either more quickly or more slowly.
There is also more diffusion with higher velocity. The groundwater
velocity ana retardation factors together determine whether a nuclide
will travel the given distance and therefore produce a dose at that
point. Retardation factors have the greatest impact upon the results.
High retardation factors not only decrease the spread of nuclides into
the groundwater, but also are associated with lower nuclide
concentrations in the water, because high retardation results from
increased sorption on the rocks.
Witn high retardation factors, nuclides move so slowly that their
concentrations are reduced very much before they travel as much as
20 meters in the aquifer. Significant contamination is limited to a
very small portion of the aquifer so that our calculations show no
areas contaminated enough to give more than 0.5 rem/yr. When nuclides
are not sorbed, so that they move as fast as the water (retardation
factor of one), doses are high over very large portions of the aquifer.
7
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Chapter 2
Introduction
2.1 Purpose of the Report
This report addresses the problem of assessing annual doses that
might be received by individuals as the result of disposal of
high-level radioactive wastes (including spent fuel) in a mined
geologic repository. Our attention has been restricted to this
particular disposal system because it is further developed than any
other and is the only system for which a useable amount of data is
available. Consideration of a particular disposal method does not
indicate that the Agency favors or endorses that method, but merely
that the Agency is trying to establish the potential effects of one
system which might be employed.
The assessment of a generic, unbuilt and undesigned disposal
system can be made only be modeling. The model we have selected
considers the entire disposal system, including the radionuclide
content of the waste, engineered barriers, the containment ability of
the host rock formation, the geospheric transport pathways, and the
biospheric and human transport pathways.
This report is one of three complementary reports presented as
support for the Environmental Protection Agency's (EPA) development of
generally applicable environmental standards for the disposal of
high-level and transuranic radioactive wastes. In it we evaluate the
highest annual dose rates that individuals exposed to releases from a
deep mined geologic repository might receive. The other two reports
describe the population risks in the first 10,000 years from releases
from a deep mined geologic repository (SmC 82) and the environmental
pathways by which the released nuclides affect people (SmO 82). In
this report we use the same repository, the same environment, and the
same release mechanisms used for the population risk report.
C.B. Smith, et al. (SmC 82) selected reasonable characteristics for the
Preceding page blank
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repository system and for the release modes from a spectrum of values
given by Arthur D. Little, Inc. (ADL 79). Values were selected that
would be achievable by technology or In nature, and that were conser-
vative (i.e., would give larger releases) so that the performance of
the repository modeled In the report would probably be poorer than
would be expected from an actual repository; SmC 82 gives the
justification for the selection of values. Since we have used Smith's
values, the doses we calculate in this report are probably higher than
those that would be expected from an actual repository. We use only
two of the environmental pathways modeled by J.M. Smith, et__al_. (SmJ 82),
drinking water and breathing air. The pathways employed in this report
use the'same parameters used in SmJ 82.
High-level and transuranic waste disposal systems must isolate
these wastes from the accessible environment for a very long time.
Most releases of radionuclides would occur as a result of unintentional
or unplanned events, either natural or caused by people. We have made
our analysis of highest annual individual dose rates for releases
initiated in the first 10,000 years. After that time doses to
individuals would be lower because of the reduction in quantity of many
important radionuclides by radioactive decay.
2.2 Plan of the Report
Chapter 3 is a general description of our analysis of individual
doses. We describe the disposal system, including the repository, the
wastes, and the environment. We also describe events that can release
radionuclides to the environment and select release scenarios at
various times in the repository history. In these descriptions, we
select values for the characteristics of the wastes and of the disposal
system as input parameters for the dose calculations. We also describe
the pathways by which radionuclides can reach people and the way in
which we calculated the resulting doses.
In Chapter 4, we consider the quantities of radionuclides released
by the initiating events and their movement through the environment
10
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to people. In Chapter 5 we present the projected annual dose rates
that might be incurred by individuals as a result of radionuclide
releases from the generic repository with selected characteristics. We
also present the extent of contaminated environment. In Chapter 6 we
present our calculations of how varying different system
characteristics would affect our projections of doses to individuals.
We did not assess the individual doses from every one of the broad
spectrum of events that might occur. Instead, we have considered a
small subset of all possible events, which we believe span a reasonable
range of circumstances and adequately illustrate potential consequences.
These events were chosen to include two small releases with a
relatively high probability and a larger release with relatively low
probability. Each event was examined at four occurrence times, repre-
sentative of the early period when short-lived fission products are
significant, of intermediate periods* and of the later period when the
waste is dominated by long-lived fission products and actinides. The
analysis addresses the impact on individuals of unplanned, although not
unforeseen, events.
We expect that most releases of radioactive material from the
repository will be the unintentional result of human intrusion, such as
drilling through the repository during a search for resources, or of
natural events, such as fault movement. We must include the
probability of such releases in our assessment.
We considered radionuclide releases to those portions of the
environment that would produce the largest doses to individuals: the
groundwater stratum and the land surface immediately overlying the
repository. For convenience we will refer to the groundwater strata as
aquifers, although they may not produce enough water to serve as
sources of drinking water.
The assessment of individual doses from the disposal phase of a
waste repository is complicated by the uncertainties in the projected
activities of people and in the use of a generic site. These
uncertainties are greater than those encountered in the calculation of
11
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population doses, where the activities of many people are averaged
out. They are also much greater than those encountered in the
calculation of dose to the maximum individual from a proposed operation
which is intended to continue for a relatively short period of time.
Examples of such uncertainties are: (1) whether or not a specific site
will be associated with an aquifer suitable for use for drinking water
or as a supply of irrigation water, and (2) the probability that an
event will open a route to an exposure medium, such as land surface, or
(3) the extent of the pathway opened by a specific event.
The probability that some (or a few) individuals may actually
receive these doses can be estimated only very roughly. The following
material is therefore presented with the caveat that the results merely
indicate an upper estimate of doses to individuals.
12
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Chapter 3
Description of the Model
3.1 Introduction
In this chapter we describe the methods we used to assess the
doses that individuals might receive. First, we describe the
repository, the wastes, and the geospheric environment. Next we
discuss the kinds of events that could release radionuclides from
confinement and the pathways by which they could reach people. Third,
we describe the particular release scenarios we chose for analysis.
Finally, we provide the procedures we used for calculating dose and
contaminated areas and for estimating the probabilities that people
would receive the calculated doses.
3.2 The Disposal System
We made our assessment for a mined geologic repository containing
100,OCX) metric tons of unreprocessed irradiated (spent) fuel from
commercial power reactors. When emplaced, the fuel is contained in
35,000 individual metal containers (canisters). We selected
unreprocessed spent fuel as the radioactive waste because it contains
both the fission products and the transuranic nuclides produced in the
operation of nuclear reactors. The potential hazard from spent fuel is
greater than that from an equivalent amount of processed waste, because
of the larger transuranium content. Analysis of doses from spent fuel
gives information that is useful in assessing doses from processed
wastes and from transuranic wastes.
3.2.1 The repositories
The reference repositories are mined cavities in bedded salt or in
granite. Each repository is two kilometers wide and four kilometers
long (SmC 82). About one-fourth of the repository is mined for the
13
-------
waste, the rest being left as walls and pillars. The mined portion is
five meters thick. After the wastes have been placed in the repos-
itory, the mined areas are backfilled. We assume-that the backfill
cannot be refilled to the original density, so that it contains voids
amounting to 20 percent of its total volume, or 2,000,000 cubic meters.
In granite, the void volume fills with groundwater moving through
fractures in the bulk rock and also through shafts and boreholes
(ADL 79). All the water becomes connected throughout the mined volume
and the shafts and can be considered as one large volume: the "granite
tank".
In the salt repository, the water is expected to enter through
imperfections in shaft and borehole seals. Once the salt repository
has been closed, the salt begins to flow plastically under the weight
of the overlying salt and the other geologic formations, so that most
of the void space is eliminated. Only a small amount of the water may
remain trapped in the salt in the form of brine pockets. We assume
that each brine pocket is in contact with two waste canisters and
3
contains 0.06 m~ of brine.
The model repository in bedded salt is 460 meters (1500 feet)
below the surface. Above and below the repository layer are 50 meters
of salt, 50 meters of impermeable rock, and a 30-meter thick porous
medium (aquifer). There are 330 meters of undefined sedimentary over-
burden between the top of the upper aquifer and the surface. The
repository in granite is also modeled as 460 meters below the surface.
The granite formation continues downward indefinitely, so that there is
no lower aquifer. There are 230 meters of granite above the repos-
itory, and then an aquifer identical with the one modeled above the
salt repository. Above the aquifer are 200 meters of overburden.
3.2.2 Thewastes
We assigned the spent fuel a composition of 95.5 percent ura-
nium isotopes, 0.9 percent plutonium isotopes, 0.1 percent other
14
-------
transuranium isotopes, and 3.5 percent fission products (ADL 79). We
selected fifteen nuclides as potentially significant contributors to
human dose. These nuclides produce large doses for each curie ingested
or inhaled, have long half-lives, and are present in the waste in large
quantities. We assumed that a period of ten years elapses between
removal of the spent fuel from the reactors and its burial in the
repository. Table 3.1 lists the significant radionuclides in the waste
and their half-lives and initial inventories (ADL 79).
The inventory of most of the nuclides in Table 3.1 at any time may
be obtained from the initial inventory by simple radioactive decay
calculations. Two nuclides in the list, Am-241 and neptunium-237
(Np-237), are produced from precursor (parent) nuclides in quantities
greater than ten percent of their original inventory. Both nuclides
are formed in the chain:
We developed an "equivalent initial inventory" of these
radionuciides so that their inventory at any time could also be
obtained by simple radioactive decay calculations. In order to do
this, the initial inventory of Am-241 was increased, atom for atom, by
the initial inventory of Pu-241 to give the equivalent initial inven-
tory of Am-241. Similarly, the initial inventory of Np-237 was
increased, atom for atom, by the initial inventories of Pu-241 and
Am-241. This calculation is conservative in two ways. First, the
inventory of each daughter nuclide is increased above the actual value
for the period during which it is growing in. Second, for several
half-lives of Am-241, the same atom is counted as both Am-241 and
Np-237. Adjustment of the inventories of Am-241 and Np-237 in this
conservative way permitted use of the equations developed for
modeling. The "initial inventory" values of Am-241 and Np-237 in
Table 3.1 have been adjusted in this way.
At 200 years after repository sealing, the shortest time used in
the calculations, essentially all the Pu-241 has become Am-241, so that
this part of the approximation introduces no error. By 1500 years,
15
-------
Table 3.1
Radionuelide Data
Nuclide
Half-life
(Years)
Initial inventory
(Curies)
C-14
Sr-90
Zr-93
5.73E+03
2.88E+Q1
9.SOE+05
5.62E-KJ4
6.00E+Q9
1.87E+05
Tc-99
Sn-126
1-129
2.10E-K35
l.OOE+05
1.70E+07
1.43E-KJ6
5.60E+04
3.77E+03
Cs-135
Cs-137
Np-237
3.00E+06
3.00E+01
2.14E+06
2.23E+04
8.64E+09
1.21E+05*
Pu-238
Pu-239
Pu-240
8.90E+01
2.40E+04
6.76E+03
2.19E+08
3.31E+07
4.89E+07
Pu-242
Am-241
An-243
3.79E+05
4.68E+02
7.65E+03
1.74E+05
4.02E+08*
1.72E+06
*Equivalent initial inventory (see Section 3.2.2)
16
-------
90 percent of the Am-241 has become Np-237, so that the overestimation
of the Np-237 introduces a small error into the calculation of doses
from this nuclide. The overall effect, however, is very small, because
we calculate that Np-237 is a minor contributor to doses before 3350
years.
The persistence of the radioactive material in its solid form is
determined by the canister life, the waste matrix leach rate, and the
solubility of the nuclide in water. The canisters eventually fail by
corrosion in the repository water. We assumed they would last 100
years in the salt repository and 500 years in the less corrosive
granite repository water. For convenience in making our calculations,
we assumed that all canisters would fail completely at the same time.
Unce the canisters have failed, the wastes come into contact with any
water in the repository and radionuclides begin to enter the water.
The maximum rate at which any nuclide can enter the water is determined
by tne leach rate of the waste, defined as the fraction of material
dissolved from the high-level waste matrix during a given period of
time. We assigned a value of 10 per year (SmC 82) for the leach
rate. Some nuclides cannot enter the water as rapidly as the leach
rate would indicate, because they have a limited solubility in
repository water. We assumed that the elements uranium, plutonium,
neptunium, and technetium would be present as tetravalent oxides in the
repository, and that americium would be present as trivalent oxide.
These elements will be in these forms in a chemically-reducing
repository environment (SmC 82). Under these conditions uranium,
plutonium, neptunium, and technetium are soluble to the extent of one
milligram per cubic meter of water (one part per billion) and amerlclum
is soluble to the extent of 50 grams per cubic meter of water. With
these values, americium concentration is limited by solubility only in
the very small quantities of water in brine pockets; plutonium,
neptunium, and technetium concentrations are always limited by
solubility. Table 3.2 gives the solubility values for each nuclide,
expressed as curies per cubic meter.
17
-------
Table 3.2
Solubility Limits and Retardation Factors
Solubility Limit'
Retardation Factors
Nuclide
C-14
Sr-90
Zr-93
Tc-99
Sn-126
1-129
Cs-135
Cs-137
Np-237
Pu-238
Pu-239
Pu-240
Pu-242
Am-241
Am-243
(Ci/rn3)
NA
NA
4.1E-06*
1.7E-05
3.0E-02
NA
NA
NA
7.QE-07
.NA
6.0E-05
2.2E-04
4.0E-06
160
10
Low Values*^
1
1
10
1
10
1
1
1
100
100
100
100
100
100
100
High Values^
10
100
10,000
1
1,000
1
1,000
1,000
100
10,000
10,000
10,000
10,000
10,000
10,000
Notes:
*4.1E-06 = 4.1 x 10~6.
NA ° not applicable, i.e., nuclide concentrations are not limited by
solubility.
1) SmC 82
2) AOL 79
18
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3.2.3 The environment
Releases to the land surface and to groundwater are the most
important routes through which individual doses may be incurred. The
highest doses would come from the land surface and groundwater
immediately above the repositories. Land surfaces do not have special
characteristics that are important in the calculation of maximum
individual doses, but groundwater strata do.
One important characteristic of groundwater in the calculation of
individual doses is the velocity with which a nuclide moves in the
groundwater. Groundwater moves through a porous rock with a velocity
that depends on the permeability of the rock, the horizontal gradient
driving the flow, and the void fraction or porosity. The velocity is
given by the equation (AOL 79):
where, V-j is the interstitial velocity,
K is the permeability,
i is the gradient, and
e is the porosity.
We assumed that we could model the aquifer by an equivalent porous
permeable rock, with a porosity of 0.15, a permeability of 31.5 meters
per year (10 centimeter/second), and a horizontal gradient of 0.01
(SmC 82, ADL 79). With these parameters, the interstitial velocity of
water in the aquifer is about 2.1 meters per year (m/yr). We also
assigned a gradient of 0.01 to the vertical flow between the two
aquifers in the bedded salt repository system.
Some nuclides move in groundwater with the same velocity as the
water. Others move more slowly because they become attached to rock
mineral surfaces and move with the water only while they are not
attached. The ratio of the water velocity to the nuclide velocity is
called the retardation factor. We used a reference set of
conservatively chosen retardation factors (SmC 82). Table 3.2 gives
these factors for each radionuclide and also a less conservative set
(AOL 79) that we used in testing the effect of changing system
characteristics. A radionuclide with a retardation factor greater than
19
-------
one would migrate more slowly than the aquifer water and would have a
velocity equal to the aquifer water velocity divided by the retardation
factor.
3.3 Initiating Events and Release Modes
Arthur D. Little, Inc. (ADL 79) described a number of failure
elements, processes or events that could result in radionuclide
release. Table 3.3 lists these in approximate order of decreasing
probability. We selected future drilling, fault movement, and shaft
seal leakage for analysis. Future drilling represents a rather likely
initiating event that would release small quantities of the waste.
Fault movement represents a rather unlikely event that would release
larger quantities of radioactive material. Shaft seal leakage is an
expected process that releases quantities of the waste similar to those
released by drilling.
We did not consider other events for one of two reasons. First,
some events are very unlikely, although their consequences might be
very high. We omitted vulcanism, meteorite impact, and igneous
intrusives for this reason. Their probabilities of occurring, in any
reasonably well-selected location, are so small that we do not believe
they should be a basis for regulatory action. The other reason for
eliminating some initiating events is that the doses that would be
associated with them are similar to, or less than, doses from the
events that we did consider. We eliminated releases through boreholes
sealed during repository construction, through undetected pre-existing
boreholes, and through bulk rock because we believe the resulting doses
would be no greater than those from future drilling. We believe
repository builders, knowing the dangers of the waste materials and
operating under strict regulation, will seal their boreholes better
than people drilling for resources in the future would. Undetected
pre-existing boreholes would most probably be in the unmined portion of
the repository; otherwise they would be detected. They would therefore
not be in direct contact with the wastes and releases through them
would be small. The radionuclides released by flow through bulk rock,
20
-------
Table 3.3
Failure Elements and Associated Probabilities
Failure Element
Annual Probability ofOccurence
for repository
for repository
in bedded salt
in granite
Expected Processes
Flow through bulk rock
Shaft seal leakage
Borehole seal leakage
0
1
1
Unplanned Events
Undetected boreholes
Future drilling* '
into repository
direct hit on waste
3E-03
0.02
2E-05
3E-03
2.5E-03
2.5E-Q6
Breccia pipe
first 500 yr after sealing 0
beyond 500 yr IE-08
Fault movement EE-08
Volcano 1E-10
Igneous intrusives 2E-10
Meteorite impacts 4E-11
0(2)
0(2)
2E-08
1E-10
1E-10
4E-11
Notes:
(1) Primarily from resource exploration
(2) Breccia pipes do not develop in granite; they are the result of
deep dissolution processes in bedded salt which can lead to
collapse of overlying material (ADL 79).
21
-------
although probably somewhat larger In total amount than those released
through a future borehole, would be released through the entire aquifer
and so the concentration would nowhere be as high as that from a
borehole. Finally, we did not consider release through a breccia pipe
because the releases would probably be smaller than those from
faulting, and the probabilities are more or less the same.
The pathways created after the events considered lead to two
release points—the land surface and an aquifer (ADL 79). We omitted
releases directly to air, which occur only as a result of events with
extremely low probabilities, such as meteorite impact and volcanic
activity. We also omitted pathways to surface water because it would
not be difficult to avoid repository sites where the hydraulic pressure
in the groundwater system, projected over conditions in the 10,000 years
following repository sealing, would not be artesian — that is, it would
not be high enough to bring groundwater to the surface spontaneously.
We considered that radionuclides in groundwater reached people
only when they drank water. We assume that a regulatory agency will
reject sites where the groundwater formation would produce enough water
to be useful for irrigation within the first 10,000 years after repos-
itory sealing.
The model aquifer is a very poor producer of water. The capacity
of an aquifer to deliver water through a well is given approximately
(Ha 62) by the equation:
2irKa m(Ah)
(3'2)
where, Q is the volume flow of well water (m /yr),
K, is the permeability of the aquifer (m/yr),
a
mis the thickness of the aquifer (m),
Ah is the hydraulic head (m),
r is the radius of influence (m), and,
r is the radius of the well (m).
22
-------
With the aquifer values given in Sections 3.2.1 and 3.2.3, a well
radius of 0.1 meter (m) (4 inches), an assumed radius of influence of
1000 m, and a h value of 3.3 m, corresponding to a depth of 330 m
3
and a gradient of 0.01, the sustainable flow would be 2100 m /yr. If
this were used for irrigation at a rate of 0.75 m/yr (about 30 inches),
2
it would serve 2800 in , which is somewhat less than one acre. We
therefore did not include doses from eating irrigated foods in these
calculations. Radionuclides released to the land surface were con-
sidered to reach people when they breathed air contaminated with resus-
pended nuclides.
3.4 Release Scenarios
3.4.1 Drilling for resources
^
We postulated that a hole with a cross-sectional area of 0.1 m ,
corresponding to a diameter of 0.36 m (14 inches), is drilled through
the repository strata during exploration for resources, connecting the
repository to the upper aquifer and to the land surface. In bedded
salt, the hole also connects the repository to the lower aquifer. We
assume that the drillers reseal the hole to a permeability of 31.5 m/yr
(10 cm/sec) (ADL 79). This permeability value represents rela-
tively poor sealing that might be expected from drillers who are
unaware of the hazard of the radioactive wastes. We assumed that the
drillers would abandon and reseal the hole if they do not discover any
resources. If they do discover resources, we assumed they would ex-
ploit these through an opening sealed from any permeable stratum, and
that they would reseal the hole as described above after the resources
had been used.
Release to theaquifer
Release of radionuclides to groundwater is a slow, continuing
process. Leaching and dissolution slowly remove radionuclides from
solids, and low flow rates slowly transfer repository water into the
aquifer. Slow movement of radionuclides in the aquifer, combined with.
23
-------
slow releases into the aquifer, result in a gradual increase in the
amount of nuclides in the groundwater, with maximum doses at any point
generally occurring many years after the initiating event.
Movement of water in a porous geologic stratum is controlled by
convection and diffusion; for each nuclide introduced at a single
point, the subsequent concentration varies with space and time. Upon
reaching an aquifer, the nuclide moves downstream from its point of
origin (the borehole). Simultaneously, it spreads transversely across
the aquifer, contaminating a parabolically-shaped area. At some future
time, according to our hypothesis, an individual may unknowingly drill
a well within the contaminated area to obtain drinking water. Our goal
is to estimate the dose which this individual would receive from
drinking the contaminated aquifer water. Because each nuclide diffuses
at its own rate, depending on the extent to which it is adsorbed by the
aquifer minerals, the description of the system is very complex.
We developed two scenarios involving releases to the aquifer by
drilling, under the assumption that they would be representative of
those release modes having potentially severe consequences for
individuals. In the first scenario, we postulated that the waste from
a single canister is penetrated. Since we assume that the canisters
are emplaced five meters apart and the drill has a diameter of 20 centi-
meters (ADL 79), we conclude that the drill cannot strike waste from
two separate canisters. The drill continues downward at least until it
strikes the underlying aquifer, if any. In both of our repositories,
the upward flow of water to the aquifer is driven by the heat produced
by the decay of the radioactive waste, which sets up a thermal buoyancy
gradient. In salt there is another driving force, the connection of
the underlying aquifer with the overlying aquifer, which produces an
hydraulic gradient. We assume, for conservatism, that the hydraulic
gradient is upward and therefore adds to the buoyancy gradient. The
rate of water flow to the aquifer is proportional to the total upward
gradient and to the permeability and flow area of the borehole. The
water removes a fraction of the waste nuclides and carries them up into
the overlying aquifer.
24
-------
In the second scenario, we assume that the canisters have failed
prior to the initial drilling operation, and that their contents have
been partially leached and dissolved into a brine pocket in a bedded
salt repository, or into the granite tank. We postulated that some
repository water moves to the aquifer with the groundwater flow. We
present the equations for both scenarios in Section 4.1,
Release to the land surface
Radioactive material may also be brought directly to the land
surface by drilling, and then dispersed into the atmosphere. The drill
may either hit waste directly or may penetrate the water volumes sur-
rounding the wastes in the repository, as described above. A direct
hit on the waste moves a fraction of the material directly to the land
surface. We assumed that this fraction was 15 percent of the contents
of one canister (ADL 79). Similarily, when a drill penetrates into the
repository water, it brings some of this water directly to the land
o
surface. We assumed that 200 m would be brought to the land surface
from a granite repository and that the entire contents, 0.06 m , of
one brine pocket would be released to tne surface from a salt repository
(ADL 79). The entire contents of the brine pocket reach the surface
because the pocket is under pressure from the overlying geologic
formations.
The waste material brought to the surface may be disposed, it may
be covered by other residue from the borehole, or it may lie on top of
the residue pile. The latter provides the most conservative estimate.
The material is assumed to be a point source. We did not calculate the
direct radiation dose from this release, which may be very large, be-
cause it depends on the way the material is handled, on the length of
time the drillers are exposed, and on other incident-specific factors;
also, since in all likelihood only the drillers would be involved, and
not the general public, we did not consider this accident to be per-
tinent to this work. We did calculate the consequences to those indi-
viduals who inhale airborne radioactivity at various distances from the
borehole and various times after the event. It is not likely that these
25
-------
exposures can be avoided once the waste material has been suspended in
the atmosphere. We discuss transport of the released nuclides in
Section 4.3.
3.4,2 Faulting
Faulting can dramatically change the permeability of the host rock
and provide a pathway for release of radioactive material to the over-
lying aquifer. The faulting event is postulated to open communication
between the repository and an aquifer along a line that runs the full
length of the repository, thus involving a larger amount of waste than
drilling. The faulting event does not release radionuclides to the
land surface, since we assume the regulatory agency would not permit
selection of a site where the supply aquifer is under such pressure as
to be artesian.
As in the case of drilling, the flow of water to the aquifer is
driven by the heat produced by decay of the radioactive waste, and, in
salt, also by the hydraulic gradient between the underlying and over-
lying aquifers. The rate of water flow to the aquifer is proportional
to the upward gradient, permeability of the host rock and overlying
strata, and the flow area of the fault, unless flow is limited by the
ability of the aquifer to provide water.
Arthur D. Little, Inc. (ADL 79) described a faulting event that
opened a space one meter wide filled with rubble across the entire
extent of the repository. In our analysis, we considered that the zone
would affect a 10-meter wide space. The fault could cross the aquifer
in any direction. A fault in the direction of the aquifer flow would
produce the highest individual doses, because wastes from several
individual canisters along the fault would reach a point where dose is
measured. A fault across the aquifer would produce lower maximum
doses, but might cause contamination of a greater area. The conse-
quences of faults at intermediate angles would fall between those of
the faults along and across the aquifer. The fault in the direction of
the aquifer was selected for examination because it would produce the
highest individual doses. We considered two faulting scenarios.
26
-------
In one, the fault strikes and breaks a row of canisters; in the other,
canisters have failed before the fault develops and the contents of two
or more rows of failed canisters are combined 1n a tank. Only the
releases from a fault intersecting water in the granite tank are
presented here, since they are much larger than releases restricted to
direct effects on canisters.
As in the case of a drilling release from a granite tank
(Section 3.4.1), the rate of entry of a radionuclide into the aquifer
is determined fay the concentration of the radionuclide in the tank and
by the flow rate of water into the aquifer, in this case through the
fault. For large faults, the flow is limited by the capacity of the
aquifer to receive water, not by the capacity of the fault to transmit
•3
it. This limit is about 18,000 m /yr, which is about one percent of
the volume of the granite repository water. Approximately one percent
of the contents of the repository tank, therefore, are brought to the
aquifer every year. The concentration of nuclides in the tank increases
with time after canister failure. A detailed mathematical discussion
of the movement of radionuclides into and through the aquifer after
faulting is provided in Section 4.2.
3.5 Dosimetry
We calculated the annual dose equivalent (hereafter referred to as
dose) rate to red bone marrow, in rem per year (rem/yr), to individuals
from drinking contaminated water. We also calculated the annual dose
rate to the lungs of individuals from breathing contaminated air. We
did not assess exposure to direct radiation from contaminated surfaces
or from submersion in the atmosphere because they are small compared to
doses from drinking water and breathing air. Use of the annual dose
rate facilitates comparison with the limits for individual dose in
other EPA regulations such as those for operations in the uranium fuel
cycle (40 CFR 190) and for drinking water (40 CFR 141) and in Federal
guidance.
Calculating the annual dose rate to a single organ underestimates
total risk to an individual. We believe this underestimation, for these
27
-------
bone-seeking nuclides, is less than a factor of two. This under-
estimation, considering the uncertainties in the input parameters to
the calculation, would not change the decisions made in the
regulation. Methods for calculating total risk to an individual were
not available when we made these calculations,
For both ingestion and inhalation, the dose equivalent rate,
H'j^, to organ k from nuclide i via pathway j can be expressed as:
H'jik = cji UJ Djik (3-3)
where, c,-.j is the concentration of the i'th nuclide in the j'th
medium,
Uj is the annual intake of the j'th medium, and
DJ.JIJ is the dose equivalent conversion factor (rem/curie) for
the i'th nuclide by the j'th pathway to the k'th organ.
Table 3.4 gives the dose equivalent conversion factors (DECF) used
for inhalation and ingestion of selected nuclides. The values of
DJ.JIJ were obtained from Killough et afl_ (Ki 78) and Dunning et al
(Ou 79). They give these DECF's for 22 target organs expressed as
50-year dose commitments from the intake of one curie. These values
are also the annual dose rates in the 50th year from chronic intake at
a level of one curie per year for fifty years (ICRP 59).
There are three pertinent DECF's for a nuclide, one for ingestion
and two for inhalation. The DECF for ingestion is designated by
Dwik' and ttlose f°r inhalation by
3.5.1 Choice of organs
We calculated the annual dose rate to red bone marrow for
ingestion and lung for inhalation for each nuclide and then summed over
the fifteen nuclides. We selected red bone marrow as the primary organ
of interest for ingestion because there is a large risk per rem for
this organ and because many of the nuclides of interest are "bone
seekers." (Ce 69).
We selected the lungs as the primary organ of interest for
inhalation. When waste is released directly to the land surface by a
-------
direct hit it is transported as is in a relatively insoluble form. The
proper model for inhalation is therefore uses the most insoluble form,
i.e., Class Y (Table 3.4). For any nuclides that do not have Class Y
DECF's, we used the class giving the highest DECF, usually Class W.
When waste is released to the land surface by drilling into repository
water, the nuclides are usually soluble. We selected appropriate reten-
tion classes, using the discussions of Killough (Ki 78). In case of
doubt as to the appropriate class, we used the more conservative
(higher dose) values. We selected a particle size of one micrometer
activity median aerodynamic diameter (WAD) for all inhalation
dosimetry.
3.5.2 Annual dose rates from drinking water
Equation 3.4 gives tha annual dose rate associated with drinking
water having any radioactivity concentration. The value of U. for
ingestion of water is given as 1.65 liters per day (ICRP 75), or
0.60 m3/yr. The
be expressed as:
0.60 m /yr. The annual dose rate from drinking water can therefore
0'60cwi Dwik' <3'4>
The concentration, cwl-, is obtained from equations 4.415 4.43,
4.45, or 4.47 when the nuclide reaches the aquifer through a small
channel, and from equation 4.52 or 4.54 when it is introduced over the
entire area due to faulting. If c.H is in Curies per cubic meter
, wi
(Ci/m )» H'w1k is in rem/yr.
3.5.3 Annual dose rates from inhalation
Individuals may receive a dose as a result of inhaling wind-blown
radioactive material suspended in the atmosphere following a release
from the repository directly to the land surface. Once the air concen-
trations, X-, have been obtained, the dosimetry is:
H'bik = Dbik ub xi (3.5)
where, 05^ is the inhalation DECF for nuclide i (rem/Ci),
% is the breathing rate (m3/yr) and,
X-| is obtained from equation 4.55.
29
-------
Table 3.4
Dose Equivalent Conversion Factors
(rem/Curie)
Ingestion
Inhalation
Nuclide
C-14
Sr-90
Zr-93
Tc-99
Sn-126
1-129
Cs-135
Cs-137
Np-237
Pu-238
Pu-239
Pu-240
Pu-242
Am-241
Am-243
Bone
Marrow
3.40E+03
4.30E+05
3.00E+02
3.20E+02
8.60E+04
9.40E+02
1.10E+04
7.40E+04
6.20E+06
1.70E+05
1.90E+05
1.90E+05
1 . 80E+05
6.40E+06
3.20E+07
Class Y
Lung
6.18E+00
8.54E+06
5.85E+04
5.22E+04
1.27E+06
7.88E+02
6.40E+02
1.62E+04
2.90E+08
3.09E+08
2.94E+08
2.95E+08
2.80E+08
3.13E+08
3.03E+08
Class W
Lung
6.18E+00
4.92E+04
3.08E+04
5.22E+04
1 . 27E+06
7.88E+02
6.40E+02
1.62E+04
3.00E+07
3.20E+07
3.00E+07
3.10E+07
2.90E+07
3.20E+07
3.10E+07
30
-------
3,6 Nethodof Calculating Dose
We calculated the dose to a person at preselected times and
places. By the very nature of the digital computer, the calculations
must be done at discrete points. We limited the number of calculations"
both to save computational time and to keep the output to an amount we
could present in a readable format. We selected times from 10 to
10,000 years after the event. In addition to the decade values of 10,
100, 1000, and 10,000 years, we calculated for the intermediate times
20, 50, 200, etc. We started the calculation of annual dose rates ten
years after the drilling release and twenty meters from the drilling
point. Doses incurred earlier than 10 years after the release do not
differ significantly from those at 10 years because the long-lived
nuclides involved decay only slightly in that time.
For releases to groundwater from drilling, we selected distances
from 20 to 4000 meters downstream from the point of introduction, the
borehole. We calculated the dose due to each nuclide at the
preselected time and distance, and then summed over all nuclides.
These calculations give the dose to a person who drinks water from the
aquifer at the preselected time and distance. We did not calculate
annual dose rates at distances less than 20 meters from the borehole
because such calculations would not be representative of doses received
by drinking the water. Wells draw water from a considerable area of an
aquifer, A well drilled close to the borehole would be drawing water
from an area including some uncontaminated areas upstream of the
borehole. The probability that a well would be drilled in the area
between the borehole and 20 meters away is small. We also calculated,
for each preselected time, the area that would be sufficiently
contaminated to cause a person who drinks the water to incur a dose
above a specified level, e.g., 0.5 rem/yr. We did this by calculating
the transverse distance, y, for each preselected distance, x, at which
the dose would equal the preselected dose level. The set of x and y
values defines an area contaminated to the specified dose level. This
area was approximated by a set of trapezoids symmetrical about the
x-axis.
31
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For releases from faulting, we also selected distances from 20 to
4000 meters. These distances, however, are from the upstream boundary
of the repository, since there is no introduction point, but instead a
release all along the length of the repository.
For the land surface releases due to drilling, we also calculated
the dose at preselected times and places. In this case, since all the
nuclides move in the same way in space, we calculated the area
contaminated at any given time simply from the distance to which the
specific level of contamination had reached.
3.7 Event Times
To facilitate the analysis of individual dose over the 10,000-year
time span, we divided the time into four periods as follows (midpoints
shown in parentheses); 100-300 (200), 300-1700 (1000), 1700-5000
(3350), and 5000-10,000 (7500). These periods are dominated, in
general, by the short-lived fission products, by Am-241, by Am-241 and
Am-243, and by Am-243 and Pu-239, respectively. Because it is
impractical to calculate individual doses for all possible event times,
the midpoints are taken as the event times; we assumed they are
representative of their respective periods with regard to the expected
consequences of the various release scenarios. We made no calculations
for events after 10,000 years, because the reduced inventories would
result in substantially lower doses than would be incurred from events
prior to 10,000 years.
3.3 Risk and Probability
The risk that the radioactive waste presents to any individual
depends not only on the dose levels to which a person would be exposed,
but also on the probability that the person will actually incur them.
The important factors affecting this probability are:
1. the likelihood that the contaminating event will occur;
and
2. the likelihood that one or more individuals will be
exposed to the contaminated medium.
32
-------
The second likeiihood, in turn, depends on the quantity of the
medium that is contaminated and on the extent to which the medium is
used.
3.8.1 Probability of contamination
Drill ing
We assumed a 100-year period of institutional control, during
which there would be no drilling, Arthur D. Little, Inc. (AOL 79)
postulates that after the initial 100 years, there would be drilling
somewhere in the repository area, once every 50 years in bedded salt,
or once every 400 years in granite. The drills would either strike
waste directly or would penetrate into the repository water. Drilling
into the repository water produces most of the risk from drilling,
since direct hits on waste are much less likely than penetrations into
repository water (AOL 79).
The Arthur 0. Little drilling frequency estimates are very
imprecise, as are all predictions of future human activity.
Nevertheless, the probability of some drilling intrusions into any
repository seems to be high. For modeling purposes, we may assume that
drilling will contaminate the aquifer.
Faulting
Fault movement, in contrast to drilling, is an unlikely event.
Arthur D. Little (ADL 79) has given a postulated annual frequency of
-8
fault movement of 2 x 10 (once in 50 million years) for a
repository in either bedded salt or granite. Hence, the likelihood of
a fault in 10,000 years is about 0.02 percent.
3.8,2 Probability of exposure
Releases to the land surface
The extent to which people are exposed to this source of radiation
depends on how many people use the land and, to some extent, on the way
in which it is used. For the purposes of this generic evaluation, we
33
-------
-5
use the average world population density of 6.7 x 10 people per
square meter (SmJ 82), a value somewhat higher than most other
population densities. For example, the rural U.S. population in 1970
was about 54,000,000 while total farm acreage was 1,066,000,000
(Wo 77). The corresponding population density is 1.25 x 10"5 people
per square meter. Population density of the contiguous United States
is 2.6 x "0 people per square meter. Regional U.S. values range
from 1.2 x TO"5 1n the West to 12 x 10"5 in the Northeast,
Releases to the aquifer
The extent to which people will be harmed by releases to aquifers
depends on the doses they would incur by using the aquifer water, the
amount of the aquifer contaminated, and the extent to which the aquifer
water is used. The extent to which the water is likely to be used
depends on the population density in the area and the availability of
other water sources for that population. We do not know either of
these factors, because we cannot predict future populations and we do
not know what location will be selected for the repository. We
estimated a general probability that a well will be drilled in an
aquifer similar to the one modeled in this report, using the frequency
of water well drilling in the United States. We calculated in
Section 3.3 that a well drilled in our aquifer would produce a
sustainable flow of 2100 m /yr, about one gallon per minute. We
found (NW 79) that about one-half of one percent of the 500,000 water
wells drilled annually (Ge 73) yielded less than ten gallons per minute
and were more than five hundred feet deep. We doubled the frequency to
one percent, or 5000 wells per year, to allow for possible greater use
of groundwater in the future. If these wells were drilled uniformly
in the 7.8 x 10 hectares of the United States, there would be
6.4 x 10 wells per hectare per year. We used this frequency,
based on shallower, more productive aquifers than our model, as a
conservative estimate for the frequency of drilling into our aquifer.
34
-------
There is a fairly high probability, over a long time, of one or
more wells being drilled into an aquifer that is contaminated for a
long time. For example, if we use the frequency of 6.4 x 10 wells
per nectare per year for 10 hectares contaminated for 10,000 years,
there is about a 47 percent probability that at least one well will be
drilled into the contaminated area sometime in the 10,000 years.
Although the probability over a long time of drilling a well into
a contaminated aquifer is high, the risk is spread over all the people
living during this time, with a smaller risk to any individual. For a
general estimate of the risk to an individual we use the probability
per hectare of drilling into the aquifer during a seventy-year
lifetime. The frequency of drilling then becomes (70) x (6.4 x 10" )
-4
or 4.5 x 10 per hectare.
35
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Chapter 4
Radionuclide Release and Transport
We divided our model for annual dose rate calculations into three
stages; (1) releases from the repository, (2) concentrations in the
environment, and (3) ingestion or inhalation of radionuclides by
exposed individuals. Stage three was covered in Section 3.5, In this
section, we develop equations that describe the processes of stages one
and two.
The representative release events we analyzed are (1) releases to
the aquifer due to drilling and subsequent borehole seal degradation,
(Section 4.1), (2) releases to the aquifer due to faulting, (Section 4.2),
and (3) direct releases to the land surface (Section 4.3).
4.1. Release to the Aquifer due to Drilling
In this set of scenarios we considered resource exploration only
within the physical boundaries of the repository and drilling events
through the upper aquifer, through the repository, and into the lower
aquifer, in the cases where one exists. We expect groundwater to flow
through the resulting borehole into the upper aquifer. If no lower
aquifer exists, as in the granite repository, the flow is induced
entirely by thermal buoyancy. Where there are both an upper and a
lower aquifer, as in the bedded salt repository, we conservatively
assume that an upward hydraulic gradient exists between them and adds
to the thermal gradient. We expect part of the radionuclide inventory
contained in the repository to be either dissolved or leached and
transported by this groundwater flow to the upper aquifer.
We examined two drilling scenarios: (1) penetration into the waste in
a single canister and (2) penetration into repository water containing
waste dissolved or leached from failed canisters. The mathematical
treatments of the release rates are described in the following
section. The subsequent transport of released radionuclides through
the aquifer is the subject of Section 4.1.2.
Preceding page blank
-------
4.1.1 Releaserata from the repository
Radioactive material is released from the repository following
dissolution of waste radionuclides by repository water. The rate of
removal of a radionuclide from the solidified waste into the repository
water may be governed by the leach rate. Some radionuclides cannot be
dissolved as readily as the leach rate would allow, because their
solubility in the water is limited. In addition to leach-limited and
solubility-limited release rates, we also consider the case where the
entry of each nuclide into the repository water was limited by the
dissolution of the uranium dioxide (UCk) that constitutes the waste
matrix for spent fuel. The UOo-limited case is a special form of the
leach-limited case.
Direct hit on waste: Leaching governs release
The quantity of a nuclide at any time t after disposal of the
waste in the repository is given by the initial inventory, Q0,
corrected for radioactive decay to time "t". All equations refer to
individual nuclides unless otherwise specified.
The inventory available for release at the time of the event,
t = te' is: Q(te) = fQ0 exp(-Ate) (4.1)
where x is the decay constant, and the factor f is the fraction of the
waste affected by the drilling. Leaching and, therefore, radionuclide
release from tne waste begin when the drilling occurs, so the inventory
is multiplied by tne leaching constant, L, to give the quantity of
nuclide that leaves the repository per unit time, Q'(t), where t _> t ,
Q'(t) = fLQQ exp(-xt). (4.2)
It should be noted that equation 4.2 has not been corrected for
depletion of tne waste by leaching during the time it is exposed to
water. To make this correction, we assume, in our model, that there is
no leaching prior to the time t = tg. This is not strictly true,
since some radioactive material may leach into the repository water if
38
-------
the canisters fail before the drilling, but the assumption simplifies
the calculation. When we make this correction for leaching depletion,
we obtain:
Q'(t) = fLQQ expC-xt] exp[-L(t - te)]. (4.3)
Direct nit onwaste:Radionuclidesolubility governs release
When the quantity of water contacting the waste is sufficiently
small, the release rate calculated according to equation 4.3 is
overestimated for certain nuclides, because the concentrations of these
nuclides are limited by their solubility.
The release rate of a solubility-limited nuclide is given by the
equation:
Q'(t) = S F(t) (4.4)
where S is the solubility, Gi/tn3, the values appear in Table 3-2 and,
F is the flow rate, in/yr.
The flow rate is the product of the cross-sectional area of the
resealed borehole, the permeability of the material used in sealing,
and the gradient driving the flow:
F(t) = A K(t) 1(t) (4.5)
where A is the area of the borehole, m^;
K(t) is the borenole permeability, m/yr; and
i(t) is the hydraulic gradient.
Therefore, the release rate for solubility-limited nuclides is a
combination of equations 4.4 and 4.5:
Q'(t) = S A K(t) i(t). (4.6)
The permeability may increase with time as the borehole seal
degrades, allowing a larger flow of contaminated water to reach the
aquifer. The equation describing the permeability as a function of
time is:
K(t) =K0+ [(K')(t - te)] (4.7)
where K0 = initial permeability, (m/yr),
K1 = rate of change of permeability (m/yr*-),
t = time elapsed after repository sealing (yr),
te = event time and,
*.> V
The quantity (t - tg) represents the period over which the
borehole seal degrades. Degradation begins when the borehole is
39
-------
resealed, following the release event at te. We assume that the flow
through the sealing material begins at t , and continues until time t.
The gradient, i(t), in equation 4.5 was derived empirically
(ADL 79, SmC 82). It describes the change in the gradient between
repository and aquifer as a function of time:
i(t) = a exp(-at) + b exp(-et) + c. (4.8)
The first two terms in equation 4.8 describe the gradient caused
by the thermal buoyancy. These terms also include the effect of
temperature on the viscosity of the water. They both decrease
exponentially over time, beginning at repository closure. The last
term, c, is the hydraulic gradient between the lower and upper
aquifers. For granite, this term is zero, because there is no lower
aquifer.
Including the terms in equations 4.7 and 4.8 in equation 4.6 we
arrive at:
Q'(t) = SA[KQ + ((K')(t-te))] [a exp(-at) + b exp(-ut) + c]. (4.9)
Direct hit on waste: Uranium solubility governs release
The third possible mechanism of radionuclide release, which is
less conservative, postulates that the removal of most of the nuclides
is limited by the solubility of the UCL matrix in which the waste is
interred. Four radionuclides can diffuse through the UCL matrix, and
so their entry into water is controlled by their own leaching rates.
These radionuclides are C-14, Cs-135, Cs-137, and 1-129.
To calculate the rate of removal of the other eleven nuclides, the
•3
solubility of U-238 (g/m ) is multiplied by the volume flow rate of
the water (m Ayr) and divided by the total mass of U-238 (g) exposed
to the water:
su F(t) (4.10)
Lu = f Mu
where s is the solubility of uranium, g/m ,
F(t) is the flow rate passing through the affected fraction of the
repository, m3/yr,
40
-------
qi(t) u Q0 "Pt-^) exp[-Lu(t - te)]. (4.11)
f Is the fraction of the repository affected and,
M is the total mass of uranium emplaced in the repository, g.
L replaces L in equation 4.3 if uranium oxide solubility is assumed
to control the rate of removal, so that the rate at which a nuclide is
released is:
$
We used the approximation:
s F{t) (4.12)
q.(t) ^—iL - qo exp(-xt)
because LU (t - tfi) is always very small compared to the radioactive
decay factor times dt.
Brine pocket
When a drill strikes a brine pocket, we assume that the entire
contents are released directly to the land surface quickly (see sec-
tion 4.3.2). From that time on, water from the lower aquifer flows
through the brine pocket at a rate of a few brine pocket volumes per
year (SmC 82). This water contacts the radionuclides in the waste and
releases them to the aquifer in the same way that water contacts waste
after a direct hit (Section 4.1.1). Therefore, equations 4.3, 4.4 and
4.10 are applicable to the brine pocket releases.* The value of "f" in
equations 4.3 and 4.10 must be adjusted to allow for the assumption
that the waste in two canisters is associated with each brine pocket
(ADL 79).
Granite tank: Leaching governs release
When the canisters fail, nuclides begin to be leached and
dissolved into the repository water. The rate at which a nuclide that
* We treated the brine pocket release more rigorously in the computer
calculations by solving the differential equations of section 4.1.1
with a non-zero value of F/V. This rigorous treatment made no
difference in the calculated concentrations and doses. We present
the treatment in this section as a more easily understood method.
41
-------
is not solubility-limited dissolves in repository water at any time, t,
is given by:
dQw/dt = LQs(t) - [x + F(t)/V] Qw (4.13)
where the subscripts "w" and "s" refer to water (dissolved) and solid
(undissolved) phases, respectively, and V is the volume of repository
water.
The rate at which the nuclide leaves the undissolved waste is
given by the differential equation:
dQs/dt = -(x + L) Q5. (4.14)
Before the canisters fail, i.e., t < t , there is no leaching into
the tank, and L = 0. Likewise, before the drilling opens a borehole
through the repository, i.e., t < t , there is no flow, and F = 0.
For all realistic cases involving drilling, F(t)/V is very small (i.e.,
a very small fraction of the total granite tank is replaced each year),
and we can use the approximation F(t)/V = 0 in equation 4.13.
The solutions of equations 4.13 and 4.14, for the period before
canister failure (t < t_) are, respectively:
_ ^
Qs = QQ exp(-xt) and, (4.15)
Qw = 0. (4.16)
For the period when t > t , the solutions are:
Qs(t) = QQ exp(-xtc)exp[-(x + L)(t - tc)] and, (4.17)
Qw(t) = [Q0 exp(-xt)][l-exp(-L)(t - tj]. (4.18)
The rate of entry of a nuclide from the repository water to an
aquifer is:
Q'(t) = F(t) c(t) (4.19)
where c(t) is the concentration of the nuclide dissolved in the
repository water, which is Q (t)/V. Therefore,
Qn
Q'(t) = [F(t) -2- exp(-xt)][l - exp{-L)(t - tc)] (4.20)
where F(t) is given by equation 4.5.
42
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Granite tank: Solubility governs release
When the canisters fall and othe;- c;eo"logic characteristics are
appropriate, nuclides dissolve in the repository water until they reach
their solubility limit. The concentration of so'iubility-limited
nuclides in the repository water is simply Equal to the solubility.
The rate of their entry into the aquifer is then given by equation 4.4:
Q1 = S F(t) (4.4)
where F, the flow rate, is determined by borehole area, permeability,
and gradient, as described in equations 4.5, 4.7, and 4.8.
Granite tank: Uranium oxide solubility governs release
As in the case of a direct hit, this case is similar to
Teaching-governed releases, so that equation 4.20 applies with L
replaced by LU from equation 4.10 for all niiclides except C-14,
Cs-135, Cs-137, and 1-129.
4.1.2 Transport in the aquifer
The radionuclides introduced into the upper aquifer will be
transported downstream by the groundwater flow in that aquifer. The
following paragraphs describe the derivation of the rate of
radionuclide transport resulting from the drilling release event.
Transport is two-dimensional because we assume nuclides are introduced
uniformly throughout the thickness of the aquifer. There is no vertical
transport because there is no concentration gradient in this direction.
Basic equation
The basic two-dimensional differential equation for the transport
of a nuclide in groundwater is:
k If* ~ C° ' (° • Oc )] + C° • (vc)] ->• xkc = 0 (4.21)
where k = retardation factor,
c = concentration of radionuclide in the solution,
t* = time since radionuclide reached aquifer,
0 = vector operator,
D = hydrodynamic dispersion tensor,
43
-------
x m radionuclide decay constant and,
v = interstitial velocity of the groundwater flow.
For two-dimensional dispersion in a one-dimensional background ground-
water flow (in the x-direction), equation 4.21 can be rewritten as:
. « . o. (4.22,
In this equation, v and v denote the vector sum of the
x y
velocity components due to the background groundwater flow and the radial
flow from the borehole, and are a function of distance. D and
Jf
D are the transverse and longitudinal dispersion coefficients
2-1
expressed in rn yr .
The solution of equation 4.22 is extremely complicated. It is
apparent, however, that the component of flow velocity due to the radial
flow is significant only in the immediate vicinity of the borehole, and
becomes negligible as distance from the borehole increases. When the
radial flow effect is negligible and the positive x-axis is chosen to be
in the direction of the normal groundwater flow, the equation can be
greatly simplified by setting v = v and v = 0, where v is the
interstitial flow velocity of the groundwater.
With these assumptions, we can write equation 4.22 as:
ax ay
Convective transport is predominant over diffusion in the direction of
flow, i.e.:
3X «
By using this approximation, we overestimate the highest individual
doses and the size of the area contaminated to very high levels; we
underestimate the size of the area contaminated to lower levels.
Therefore, equation 4.23 may be further simplified by neglecting the
dispersion term in the x-direction:
!£. _ (JL\ J_S. + I !£ + xc _ n (4
at* (k ' ? k ax xc ~ u> *4'
44
-------
The above equation is to be solved with the initial condition:
c = 0 when t* = 0.
Nuclides are introduced into the aquifer only at the point
(x = 0, y = 0) at a rate Q'(t) where Q' is the release rate of the
appropriate radionuclide from the repository as given by equations 4.3,
4.4, arid 4.12, as appropriate.
Solution of transport equation
We solved equation 4.25 by superposition. First, we obtained
transverse dispersion, by solving the equation:
1C* Ax l!c* _ n (4.26)
for the case of a pulse release of radionuclide AV at t = t or
t* = 0. We denote the concentration variable by c* because it
represents only the one-dimensional concentration in the y-direction.
The solution of equation 4.26 is:
2
c*(y,t*) = Av[4ir(Dy/k)t*r1/2 exp[- JfJ. (4.27)
9 3t "3
AV must be expressed in Ci/m so that c can be expressed in Ci/m .
We consider that the pulse release Ay is actually introduced over the
short time At, and so is introduced over the length AX, which is the
distance the nuclide moves in the time At. AV is also introduced
uniformly throughout the vertical thickness, ro, of the aquifer. The
total number of curies in the pulse release is equal to Q'(t) At, which
will be distributed over the horizontal distance of AX and in the
entire thickness of the aquifer. Since equation 4-27 considers only
one unit thickness of aquifer, one may write:
jVj Q'(t) At (4.28)
m AX
and
c*(y.t*) - Q'(^ -A*. [4m(D /k) t*r1/2
exp(-xt*) (4.29)
in which AX is related to At by the velocity of the nuclide, v/k:
AX = (v/k) At. (4.30)
45
-------
Thus we obtain:
c*(y,t*) =
exp(-xt*). (4.31)
We now introduce the x-dependence of c* using the relation of x
and t*. Since the nuclide moves in the aquifer with a velocity v/k for
a time t*, and since we neglect dispersion in the x-direction:
x m (v/k)t* and, (4.32)
t* = kx/v. (4.33)
We substitute equation 4.33 into equation 4.31. We also evaluate
Q'(t) at the time "t - (kx/v)"5 since the nuclide entered the aquifer
at time "t - t*", which is "t - (kx/v)".
We then obtain;
-1/2 '
c*(x,y,t) ,
which can be simplified to:
C4*(Dy/kHkx/v)]
(4lD/v)
-i/2 .
exp(-
exp(-xkx/v). (4.34)
The concentration c* is the total concentration of radionuclide in
the aquifer, including both nuclide dissolved in water and nuclide
sorbed on rock. To obtain the actual concentration c dissolved in
water, we must first multiply c* by 1/k, which is the fraction of the
nuclide in the water, and then divide by e, the porosity, to account
for the fact that the water occupies only the pores in the aquifer
formation. With these changes, we obtain:
c(x.y,t) .
exp(-xkx/V).
The maximum downstream center-line distance to which a given
nuclide can travel is governed by its transit time, kx/v. The
concentration of the nuclide at any distance before its transit time
46
-------
being reached should be zero. In order to account for this
mathematically, we introduce the unit step function U(t - t - kx/v)
to equation 4,36, which has the following properties:
( 0 for t - t < kx/v
U(t - t - kx/v) = { e (4.37)
e ( 1 for t - tg _> kx/v.
If desired, equation 4.36 may be further simplified by introducing the
relationship between the trai
the interstitial velocity v:
relationship between the transverse dispersion coefficient, D , and
(4.38)
where Ai is the transverse diffusivity, ra.
For this generic assessment, we assumed a value of 6 m for /L.
When this relationship is substituted into equation 4.35 and the U-
fimttion included, we obtain:
exp[-x(kx/v)] U(t-tg-(kx/v)). (4.39)
4.1.3. Concentration in the aquifer due to drilling
There are four different expressions that describe the concentration
of a released radionuclide in the aquifer. We derived these by combining
the release rates developed in Section 4.1.1 with the aquifer transport
equation, equation 4.39.
The appropriate release rate equations are 4.3, 4.9, 4.12, and
4.20. We evaluate each of these equations at the time "t - kx/v", so
that we can evaluate the dose at point (x,y) at time t.
Leach-limited release from waste or brine pocket hit
We can transform equation 4,3 by substituting "t - kx/v" for "t":
Q'(t - ^f) = fLQQ exp[-x(t - kx/v)] '
exp [_L(t-te-kx/v)3 (4.3a)
47
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and combine it with equation 4.39 to give:
f LQ , /? 2
c(x,y,T) = - exp[-x(t-kx/v)] [x]-"* exp[-
exp(-x *•) exp[-L(t-te- £) U(t-tg- £)]. (4.40)
We can combine the radioactive decay factors to give:
fLQ (4WLX)-1'2 .
c(x,y,t) = — 5__I - exp(-xt) exp[-L (t-tg-^)] '
v kx
exp [-4AT] U (t-V v}- (4'41)
I*
Equation 4.41 is appropriate for determining the concentration of nuclides
which are not limited by solubility when the drill strikes waste directly
or strikes a brine pocket.
Solubility-limited releases
Combining equations 4.4 and 4.5 and evaluating at "t - kx/v", we
arrive at:
Q'(t -~) = S AK(t -^|) i(t -££) (4.42)
with equation 4.39, we obtain:
U(t-t-e(kx/v)). (4.43)
I*
Equation 4.43 is appropriate for determining the concentration of
solubility-limited nuclides when the drill strikes waste directly or
strikes a brine pocket or repository water.
Uranium oxi de-limited releases from waste or brine pocket hit
Situations limited by the solubility of the uranium oxide matrix
are similar to leaching. When we combine equation 4.12, evaluated
48
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at t - kx/v:
q,(t _kx/v) =_M_£MQ0 exp[-x{t - (kx/v))] (4.12)
with equation 4.5 also evaluated at t - kx/v:
F = A K(t - kx/v) i(t - kx/v) (4.5)
with equation 4.39, we obtain:
sn A K(t - — — ) l (t -- — ) ,, i /?
c(x.y,t) = -a - i-1^ - SL QQ exp[-x(t - M)]^]'1 /2 '
2
exp (-^l^-) exp(-xkx/v) U[t-tg-(kx/v)]. (4.44)
\r
By combining the decay terms, we obtain:
AK(t -) T(t -
— Q0exp(-xt) '
(4.45)
u
c(x,y,t) - -^- - - ^— Q0exp(-xt) '
Equation 4.45 is appropriate for determining the concentration of
nuclides when this concentration is limited by the solubility of the
uranium oxide matrix, when the drill either strikes waste directly or
strikes a brine pocket.
Lsach-limited releases from the granite tank
When we combine equation 4.20, evaluated at "t - kx/v":
Q'(t-kx/v) = F(t-kx/v)(-J) exp[-x(t-kx/v)][l-€Xp[(-L)(t - tc)]] (4.20)
with equation 4.5 and equation 4.39, we obtain:
A K(t -% 1(t -%(L
c(x9
-------
In this equation, we can combine the radioactive decay terms, obtaining:
A K(t -% 1(t -% Q
c(x,y,t) = - V mev v V ° exp(-xt) '
[1 - exp[(-L)(t-tc-*£)]] '
Equation 4.47 is appropriate for determining the concentration of
nuclides that are not limited by solubility, when the drill strikes
repository water in granite. When the nuclide concentration is limited
by the solubility of uranium oxide, the uranium leaching constant L
should be substituted for L in equation 4.47,
4.2. Release to the Aquifer due to Faulting
Faulting events differ considerably from resource exploration
drilling events. In one faulting scenario we assume a single fault
intersects the waste in a straight line in the direction of aquifer
flow, rupturing intact canisters. In the other scenario, we assume the
canisters have already failed, and activity from many canisters has
dissolved into the repository water in the backfill. This activity,
which is in a single "tank", is affected by the fault. These scenarios
differ in the fraction of the repository affected by the fault.
The faulting event opens a vertical pathway for a groundwater flow
to develop that carries radionuclides from the repository to the
overlying aquifer. The radionuclides that enter the upper aquifer are
then transported horizontally in the aquifer groundwater. As the
radionuclides are transported downstream within the region above the
repository, they will be joined by radionuclides being discharged into
the aquifer further downstream. Therefore, the radionuclide
concentration tends to increase with distance downstream, until the
radionuclides pass the edge of the repository. We have calculated only
50
-------
the concentration at the center line of the fault, as a function of the
distance downstream from the upstream end of the repository.
The faulting event may 0e mathematically modeled as equivalent to
a large number of drilling events. The concentration of radionuclides
at any distance "x" downstream in the aquifer from a borehole was
derived 1n Section 4.1.3. We calculate the concentration at any
distance "X" downstream from the upstream repository edge by summing
the effect of all the upstream releases. To do this, we replace the
borenole with an element of length dx and integrate over all
appropriate x values.
4.2.1 Leaching governs release
Equation 4.41 gives the concentration at a point x meters
downstream in the aquifer from a borehole release point for all values
of y and t , We can use this equation for the increment of
concentration, dc, at time t at the distance X from the upstream end of
the repository due to a release through the infinitesimal length dx at
a distance X from the upstream end of the repository. We can do this
by suostituting Q dx/L for Q » since that is the fraction of the
inventory available to the length dx, and by substituting the distance
9
(X-x) for x. We can also omit the exponential term in y since we
are interested only in the centerline dose value (the highest dose).
With these changes, we obtain;
fLQ dx
exp[~L(t-te- ] u[t_v zij (4.48)
where,
dc(x,t)y is the infinitesimal increment of concentration at
A
X due to the contribution of the release emerging at
x meters from the point of interest X,
L is the length of the repository,
X is the distance from the upstream end of the repository and,
the other symbols are the same as previously defined.
51
-------
To simplify the process of integration, we now substitute
z = X - x, and group all terms not involving z, so that equation 4.48
becomes:
dc(X-z,t)x Yjp exp(-xt) exp[-L(t - t )] .
mevL,(4irA..) '
n u
z~1/2 exp[-L ^|] U (t-te- ^|)(-dz). (4.49)
To obtain the concentration of a radionuclide at X and at a time T,
the time elapsed from the occurrence of the event of interest, we
integrate equation 4.49:
c(X'T) =Jdc(X-z,T). (4.50)
We can eliminate the U factor by noting that U = 0 when
z > (v/k)(T-te) and adjusting the limits accordingly. We also
reverse the limits to remove the minus sign from dz. Equation 4.50
then becomes:
,(v/k)(t-t ) .. .
c(X,T) = t ) e [z~1/2 exp(-iM.)]dz (4.51)
where T is expressed in t - te and,
t is the part of the expression independent of z:
fl_Qo exp(-U) exp[-L(t - tfi)]
The integral in equation 4.51 cannot be expressed analytically, but
we evaluated it numerically by Simpson's rule. The numerical analysis is
complicated by the fact that the integrand becomes infinite for z = 0.
Physically, this is because the diluting flow in the aquifer is
one-dimensional, with no transverse dimension, and so is equal to zero.
Since any well would have a finite size, and would draw from a rather
large area, it is reasonable to exclude a one-meter distance, so that the
concentration, with the new limits on the integral, becomes:
(v/k)(t-te)
c(X,T) = Y j [z~1/2 exp(--^-)] dz. (4.52)
1
52
-------
Wnen tne upper limit is larger than the length of the repository, it is
replaced by Ln.
4.2.2 Radlonuclide solubility governs release
The calculation of c(X,T) is done in a manner similar to that used
in section 4.2.1, beginning with the appropriate equation, equation 4.43.
In this way, we obtain an equation analagous to equation 4.48:
dc(x,t)x
exp[-xk(X-x)/v] U[t-te-(k(X-x)/v)]. (4.53)
This expression may be evaluated by the technique used in the
previous section. One additional simplification is possible — in the
calculations done for this report, a constant permeability was used, so
that K1 = 0. .The K for faulting is the permeability produced by the
fault. This premeability may be expected to decrease with time by
compaction and filling of the fault zone. Constant permeability is,
therefore, conservative.
In this case, as before, we are interested only in the annual dose
2
rates on the center line, so we may omit the exponential term in y .
We substitute z = X - x, and integrate from 0 to X. Before evaluating
the Integral, we change the limits on the integral as in section 4.2.1.
The concentration of the radionuclide at X = 4,000 m, corresponding to
the downstream end of the repository, at time T (= t - t ) is then:
(v/k)(t-te)
(4.54)
The terms in this equation are defined in Sections 4.1.1., 4.1.2, and
4.2.1.
4.2.3. Uranium oxide solubility governs release
The form of the equation in this case is identical to that for the
Teaching-governed case (Section 4.2.1), except that L is replaced by
53
-------
LU (equation 4,10) for those nuclides which are retained the Ut^
matrix. Because of this similarity, the equation is not repeated here.
4,2.4 Faultdisturbs the granite tank
The equation for the aquifer concentration resulting from a drill
striking repository water was given in equation 4.47. In developing
equation 4.20, for entry of nuclides into the aquifer when a drill
strikes repository water, we considered that removal of radioactive
material from the repository water by trie borehole flow to the aquifer
was negligible (see section 4.1.1.3.1). Since faulting causes a much
larger flow of water through the repository to the aquifer, this
approximation is not appropriate here. We included the factor F/V (see
equation 4.13} in the computer program for calculating doses from
connecting the repository water to the aquifer through a fault. The
concentration at X = 4,000 m at time t is calculated by the same
transformation and integration used in sections 4,2.1, 4.2.2, and 4.2.3.
4.3. Release to the Land Surface
Nuclides may be released to the land surface as a result of
drilling for resources. This is a point release, limited to the
drilling site. Nuclides released to the land surface can affect
individuals who breathe air contaminated by resuspended radioactive
particles and who stand on contaminated ground.
We considered two modes of release of waste material to the land
surface. One is a direct hit on waste by a drill. The other assumes
that a waste canister nas failed and that the drill then penetrates
into a surrounding brine pocket (in a salt repository) or tank (in
granite) contaminated by waste.
After the radionuclides reach the surface, the mathematical
description of their dispersion and of the surface contamination are
the same for both models. The release that occurs via an intermediate
stage (e.g., a brine pocket) is more complicated because it includes
transport of nuclides from a failed waste canister to the brine pocket
or tank.
54
-------
Radionuclides deposited on land surface are resuspended into the
air, moved by air currents, and redeposited on the ground. The
radionuclides are diluted as they move in the air and are depleted by
deposition on the ground. Estimation of dose from inhalation requires
knowledge of the air concentration. Nelson, et alL._ (Ne 78), give
equations for the calculation of the air concentration as a function of
time and distance from a point source. This air concentration
decreases with time due to depletion by radioactive decay and
deposition, and removal to the soil sink. The DECF's (Ki 76, Du 79)
give the fiftieth year dose equivalent corresponding to a constant rate
of intake over the 50-year period.
We used the primary air concentration X^, neglecting secondary
resuspension, as an approximation to the total air concentration. Using
XQ facilitates the calculation Because the time component is
separable in the function. In Table 4.1., Nelson et _al_. (Ne 78) give
values of primary (XQ) and secondary (Xi) air concentrations
at one kilometer from a ground surface point source of plutonium-239.
These values show that the secondary concentration is only two percent
of the primary air concentrations fifty years after contamination
occurred and much less before that.
The equation for the air concentration due to direct (first-pass)
dispersion from the source is (Ne 78):
X.J(r,t) = Qxr(X/Q')(r/rnr° expC-C^)2"0] exp[-xt(t - tg)] (4.55)
wnere XQ is the air concentration of a radionuclide at a
distance r from the source and at time t (after the initiating
event at te), taking into account depletion of the plume.
The subscript "o" denotes the air concentration due to primary
(first pass) dispersion of contaminated material from the point
source,
Q is the amount of radionuclide released to the ground surface (Ci),
(X/Q1) is the atmospheric dilution factor at distance r (yr/rrp),
rn is a reference distance (m),
a is the slope of log (X/Q1) vs log r, determined empirically,
rjj is the characteristic depletion distance,
xt is the total removal rate = xr + xs + x (yr~'),
55
-------
xr » resuspension rate (yr-1),
xs = rate of depletion into the soil (yr-«) and,
x = radionuclide decay rate (yr ).
X is separable into functions of r and t:
XQ (r.t) = QM N(r) S(t) (4.56)
where M = xr (X/Q1) (4.56a)
N = (r/rn)-° exp[-(r/rd)2-°] and, 4.56b
S - exp[-xt(te)5. (4.56c)
Separability of X (r,t ) makes it easy to treat nuclides
other than Pu-239, since equations for their air concentrations will
differ only in the value of x^. Separability also makes it easy to
calculate the air concentration at different distances. Parameters for
radionuclide transport were taken from Nelson et_a]_. (Ne 78). A low
resuspension rate (x = 3.15 x 1CT yr~ ) was selected as
appropriate for the borehole material brought to the surface, which
would be wet, and in a low dusting form. Furthermore, much of the
radioactive material would probably be covered by inert rock fragments
and drilling mud.
M N(r) can be evaluated for all nuclides at r = 1 km, using
Nelson's plutonium values of 1.01E-9 per second (= 3.19E-2 yr~ ) for
O ?4
xt, 1.8E-17 Q Ci/m for X° at 1 km and 1 year and,
S(te = 1) = exp(-3.19E-2) = 0.969, (4.57)
M N(r = 1 km) = 7 = T-86^17 m"3- (4-58)
The integrated atmospheric concentration, Ej, (Ci-yr/m^), around
an individual at a distance "r" over a 50-year time period can be
obtained by integration:
,50 .
Eb(r,t) = Q) Xj(r,te) dt (4.59)
,50
= QMN n) exp(-x+t ) dt (4.59a)
U v C
Ll - exp(-50v )]. (4.59b)
xt *
56
-------
Table 4.1
Primary and Secondary Air Concentrations
t-t
e
(yr) X^ (Ci/m3) xj (Ci/m3)
0.01 1.9E-17 6.0E-23
0.1 1.9E-17 6.0E-22
1 1.8E-17 5.8E-21
10 1.4E-17 4.4E-20
25 8.6E-18 6.7E-20
50 3.9E-18 6.1E-20
57
-------
The average air concentration is obtained by dividing this
equation by 50 years:
(Xjj)av(r,t) = - [1 - exp(-50xt)]. (4,60)
The dose equivalent rate after breathing air contaminated to this
average level for 50 years, is:
Hbik = H -exp(-50x)] (4.6!)
where b refers to breathing, i to nuclide i, and k to organ k. There
is an equation of this type for each nuclide and each organ.
4.3.1 Direct drilling hit on waste
In this scenario, we consider that the drill strikes solid waste,
either in a canister prior to the canister failure time, or exposed
after that time. In either event, we assume the drill removes 15 per-
cent of the waste in one canister to the surface (ADL 79). Equation 4.1
gives the total inventory of the nuclide in the repository at the event
time t . The quantity, Q, removed to the surface is:
Q(te) = 0.15 fQQ exp(-xte). (4.62)
Equation 4.62 may be substituted into equation 4.61 to obtain the
50th-year dose rate.
If the drilling event occurs after canister failure, the inventory
of nuclides in the waste would be further reduced by depletion through
leaching by the factor "exp[-L(t - t )]". We did not include this
C. L»
factor, so that our calculations are conservative to this extent.
4,3.2 Liquid from a brine pocket or granite tank
Leaching governs release
In these scenarios, we assume the waste is completely contained in
its canister until the failure time, which we assume is 100 years in
salt or 500 years in granite (ADL 79). The wastes then begin to leach
and dissolve into the repository liquid. In a salt repository, the
contents of two failed canisters leach into a common volume which we
have termed a "brine pocket." In granite, all the failed canisters
58
-------
leach into one common volume, or "tank." When a well is drilled into a
brine pocket, the lithostatic pressure results in a rapid release of
the entire contents to the surface. We simplified the model by
assuming that the release was instantaneous. The consequences of the
release depend on the time at which the hole is drilled and the volume
of the brine pocket. There are, of course, no radiological
consequences if the hole is drilled prior to canister failure.
We have already discussed the accumulation of radionuclides in
granite repository water in section 4.1.1. The differential equa-
tions 4.13 and 4.14 describe this movement. There is no flow through
the repository before the drilling event releases radionuclides to the
surface, so the (F/V) term in equation 4.13 can be set equal to zero.
Equation 4.18 then gives the quantity of a nuclide leached into solu-
tion in the repository water. We modify equation 4.18 slightly by
dividing by V, the volume of the brine pocket or granite tank, in order
to convert quantity to concentration. We also introduce the factor f
to denote the fraction of the repository exposed to the brine pocket or
tank. This gives, for the concentration at the event time t :
fQ exp(-xt )
c(te) - — y — (1 -exp[(-L)(te - tc)]). (4.63)
The fraction f is 1 in granite, since all the waste is exposed to
repository water. In salt, it corresponds to two canisters (ADL 79),
and therefore equals 2/35,000. The liquid volume V is 2,000,000 m3
3
in granite and 0.06 m in salt.
We assume a volume of 200 m (ADL 79) is released to the surface
from drilling in granite, while the entire contents of the brine pocket
are released to the surface from drilling in salt. The total amounts,
Q, released to the surface then become:
200Q exp(-xt ) (4.64)
Q- 2!oOO,000 H -exp(-L)(te-tc)]
in granite, and in salt:
Q = fQ0 exp(-xte) [1 - exp[(-L)(te - tc)]. (4.65)
59
-------
Nuclide solubility governs release
For nuclides whose entry into the repository liquid is limited by
solubility, the concentration in the brine or water is simply equal to
the solubility S (Ci/m }. The amount delivered to the surface is
then simply:
Q - 200 S {4.66}
in granite, and
Q = 0.06 S (4,67)
in salt.
60
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Chapter 5
Results of the Reference Disposal System Analysis
This chapter presents the annual dose rate and contaminated area
results from our reference disposal system. The calculations were done
using an EPA computer code (Se 81) that numerically models the release
of radionuclides from the repository (the source terra) and their
environmental transport. The code calculates the annual dose rate for
each nuclide at preselected dose times and distances, and then sums
over all the nuclides to yield the total annual dose rate for that
release. The code also calculates areas contaminated above preselected
dose rate limits. The area tables are useful indicators of the
potential health risk from the repository because the probability that
someone will incur the indicated dose is proportional to the contam-
inated area. We considered four event times: 200, 1000, 3350 and 7500
years, and used the 1000-year event as the reference time. The
reference data on the important nuclides appear in Table 5.1. The code
calculates one of two source terms, either leaching- or solubility-
limited, as appropriate. A summary table of the maximum annual dose
rates is presented in Table 5.43 at the end of this chapter.
The annual dose rate results are in the form of a computer output
that gives annual dose rates at 10 preselected distances and 13 pre-
selected times. Table 5.2 is a sample computer output for one
release. It gives the annual inhalation dose rate from release to the
land surface following drilling that hits the waste 1000 years after
repository sealing. It consists of a 13 by 10 table of annual dose
rates. The dose times appear on the left side of Table 5.2 and cover
10 years to 10,000 years after the event. The distances are listed at
the top of the table and cover 20 meters to 4000 meters. Each location
in the table contains three items: the dose rate in rem/yr, the
radionuclide that is the largest contributor to the dose and its
61
-------
Parameter
Name
Leach rate
Table 5.1
Repository System Characteristics
Parameter
Symbol
Reference
Value
10-4
Low
Value
10-5
Sroundwater
velocity
(m/yr)
Nuclide
C-14
Sr-90
Zr-93
Tc-99
Sn-126
1-129
Cs-135
Cs-137
Np-237
Pu-242
Pu-240
Pu-239
Pu-238
Am-241
Am- 243
v 2.1
Retardation Factors
Reference
Value
1
1
100
1
10
1
1
1
100
100
100
100
100
100
100
High
Value
10
100
10,000
1
1,100
1
1,000
1,000
100
10,000
10,000
10,000
10,000
10,000
10,000
0.
(k)
Low
Value
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
,21 ;
Solubility
o
(Ci/nr5)
*
*
2E-6
2E-5
0.03
*
*
*
7.2E-7
4E-6
2.2E-4
6E-5
**
160.0
10.0
High
Value
10-2
21
*Solubility so high that nuclide was leach-limited in all cases.
**Pu-238 was considered to be leach-limited in all cases, even though
its solubility may be limiting in a few cases. This approximation is
conservative.
62
-------
percent of the total dose rate. In Table 5.2, for example, the output
for a dose time of 10 years and a distance of 50 meters is:
2.96E+00
AM-241
54.2%
which indicates an annual dose rate of 2.96 rem/yr, 54.2% of which is
from Am-241, the largest contributor.
Table 5.3 shows areas of the land surface contaminated above
preselected dose rates for this release. Dose times are listed in the
left column. The five columns of data following the dose times are
4 2
cumulative areas in hectares (ha = 10 m ) contaminated above
preselected values. The area tables are given for drilling releases
only.
5.1 Release to the Aquifer Due to Drilling
Tables 5.4, 5.5 and 5.6 demonstrate the relative movement in
groundwater of nuclides with different retardation factors. These
tables are the results of three special computer model runs, one for
technitium-99 (Tc-99) only, another for tin-126 (Sn-126) only, and the
last for Am-243 only. The rate at which each radionuclide moves in the
groundwater is equal to v/k; Tc-99 flows at 2.1 m/yr, Sn-126 at 0.21
m/yr and Am-243 at 0.021 m/yr. These are average values reflecting the
fraction of time that the nuclide is immobile or is flowing with the
aquifer. When more than one nuclide is present, each will travel at
its own rate depending upon its retardation factor, K, which may have a
value of 1, 10, or 100 depending on the particular nuclide. The
numerical values in Tables 5.4, 5.5, and 5.6 are dose rates that would
result from drinking groundwater. Since the special runs, with only
one nuclide present in each, represent an artificial situation, the
values should be used only for relative purposes within one table.
Table 5.4 shows that the rapidly moving Tc-99 travels 20 meters
within ten years, 1000 meters within 500 years, and 4000 meters within
2000 years. Values at any distance decrease very slowly over time;
63
-------
Table 5.2
in
-f*
TIME (yr)
l.OOE+01
2.0QE+01
5.00B+Q1
l.OQE+02
2.00E+02
5.00B+02
l.OOE+03
2.0UE+03
5.0UI+03
1.001404
Dose Equivalent Rates (rcm/yr) from Breathing Air Contaminated by Radionuclidei
Released by Borehole Drilling
1000 Years After Repository Sealing
Drill Hits Halts
DISTANCE (metern)
20.00
1.12E+01
AM-241
54.2%
1. 10E+01
AM-241
53.91
1.06E+01
AH-241
52.82
9.91E+00
AM-241
51.01
8.71E+00
AH-241
47.41
6.1 IE +00
AH-241
36. 91
3.711+00
PU-240
42. 7%
1.73E+00
PU-240
49.8X
2.92E-01
PU-239
50.02
I. 72E-C2
PU-239
59.02
50.00
2.96E+00
AM-241
54.2%
2.92E+00
AH-241
53.9%
2.80E+00
AH-241
52.81
2.62E+00
AM-241
51.02
2.30E+00
AH-241
47.4%
1. 61E+00
AM-241
36.9%
9.81E-01
PU-240
42. 7X
4.53E-01
PU-240
49.82
7.73K-02
PU-239
50.01
4.54K-03
PU-239
59.01
100,00
1.07E+00
AM-241
54.22
1.06E+00
AM-241
S3.92
l.OJE+00
AK-241
52. 8X
9.49E-01
AM-241
51.02
8.34E-01
AM-241
47.4%
5.8SE-01
AH-241
36.9%
3.55E-01
PU-240
42.72
1.66E-01
PU-240
49.82
2,*OE-02
PU-239
50.02
1.64E-03
PU-239
59.0%
200.00
3.83E-01
AH-241
54.22
3.78E-01
AM-241
53.9%
3.63E-01
AM-241
52.8X
3.40E-01
AM-241
51.02
2.99E-01
AH-241
47.42
2.09E-01
AM-241
36.9%
1.27E-01
PU-240
42.72
5.95E-02
PU-240
49. 8%
l.OOE-02
PU-239
50.01
5.88E-04
PU-239
59.02
500.00
9.59E-02
AM-241
54.22
9.46E-02
AH-241
53.9%
9.08E-02
AM-241
52.8%
8.50E-02
AH-241
51. 02
7.47E-02
AM-241
47.4%
5.24E-02
AM-241
36.92
3.18B-02
PU-240
42.7%
1.49E-02
PU-240
49.8%
2.51E-03
PU-239
50.02
1.47E-04
PU-239
59.02
750.00
5.12E-02
AM-241
54.22
5.05E-02
AM-241
53.9%
4.85E-02
AM-241
52.8%
4.54E-02
AH-241
51.01
3.99E-02
AM-241
47.41
2.79E-02
AM-241
36.9%
1.70E-02
PU-240
42.72
7.94E-03
PU-240
49.82
1.34E-03
PU-239
50. 01
7.85E-05
PU-239
59.02
1000.00
3.25E-02
AM-241
54.2%
3.21E-02
AM-241
53.92
3.08E-02
AH-241
52.8%
2.88E-02
AM-241
51.0%
2.53E-02
AM-241
47.42
1. 78E-02
AM-241
36.9%
1.08E-02
FU-240
42.72.
5.05E-03
PU-240
49.8%
8.50E-04
PO-239
50.02
4.99E-05
PU-239
59.02
1500.00
1.70E-02
AM-241
54.2%
1.67E-02
AM-241
53.9%
1.61E-02
AM-241
52.8%
1.50E-02
AM-241
51.02
1.32E-02
AM-241
47.42
9.26E-03
AM-241
36.9%
5.61E-03
PU-240
42.72
2.63E-03
PU-240
49.8%
4.43E-04
PU-239
50.02
2.60S-05
PU-239
59.0%
2000.00
1.06E-02
AM-241
54.22
1.04E-02
AH-241
53.9%
l.OOE-02
AM-241
52.82
9.36E-03
AM-241
51.0%
8.23E-03
AM-241
47.42
5.77E-03
AH-241
36.9%
3.50E-03
PU-240
4Z.72
1.64E-03
PU-240
49.82
2.76E-04
PU-239
50.0%
1.62E-05
PU-239
59.0%
4000.00
3.22E-03
AM-241
54.2%
3.17E-03
AH-241
53.9%
3.05E-03
AH-241
52.82
2.85E-03
AM-241
51,02
2.51E-03
AH-241
47.4%
1.76E-03
AK-241
36.92
1.07E-03
PO-240
42.72
4.99E-04
PU-240
49.82
8.40E-05
PU-239
50.02
4 . 93E-06
PU-239
59.02
-------
Table 5.3
Area (ha*) of the Land Surface Contaminated
•Above the Specified Dose Rate Levels Following
a Direct Drilling Hit on Waste
1000 Years after Sealing
Time After Dose Levels (rem/yr)
Drilling (yr) 0.5 5.0 50"
10 10.5 0.57 0
20 10.4 0.56 0
50 10.1 0.54 0
100 9.5 0.51 0
200 8.3 0.44 0
500 4.8 0.24 0
1000 2.5 0 0
2000 0.8 0 0
5000-10,000 000
*1 ha = 1Q4 square meters
65
-------
Table 5.4
Example of Dispersion in Groundwater of a Huclide with a Retardation Factor of One
(All Dose Rate Values are Relative)
DISTANCE (metera)
TIME
l.OOE+01
2.00EMU
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
20.00
6.70E-06
TC -99
100. OZ
6.58E-06
TC -99
100. OZ
6.61E-06
TC -99
100. OZ
6.51E-06
TC -99
100. OZ
6.32E-06
TC -99
100. OZ
5.87E-06
TC -99
100. OZ
5.34E-06
TC -99
100. OZ
A. TOE -06
TC -99
100. OZ
3.85E-06
TC -99
100. OZ
3.43E-06
TC -99
100. OZ
50.00
0.0
NOME
O.OZ
0.0
NONE
O.OZ
4.20E-06
TC -99
100. OZ
4.14E-06
TC -99
100. OZ
4.02E-06
TC -99
100. OZ
3.72E-06
TC -39
100. OZ
3.38E-06
TC -99
100. OZ
2.98E-06
TC -99
100. OZ
2.43E-06
TC -99
100. OZ
2.17E-06
TC -99
100. OZ
100.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
2.99E-06
TC -99
100.0Z
2.95E-06
TC -99
100. OZ
2.86E-06
TC -99
100. OZ
2.65E-06
TC -99
100. OZ
2.40E-06
TC -99
100. OZ
2.11E-06
TC -99
100. OZ
1.72E-06
TC -99
100.0Z
1.53E-06
TC -99
100. OZ
200.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
2.11E-06
TC -99
100. OZ
2.05E-06
TC -99
100. OZ
1.89E-06
TC -99
100. OZ
1.71E-06
TC -99
100. OZ
1.50E-06
TC -99
100. OZ
1.22E-06
TC -99
100. OZ
1.08E-06
TC -99
100. OX
500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
1.24E-06
TC -99
100. OZ
1.11E-06
TC -99
100. OZ
9.62E-07
TC -99
100. OZ
7.77E-07
TC -99
100. OZ
6.86E-07
TC -99
100. OZ
750.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
1.05E-06
TC -99
100. OZ
9.26E-07
TC -99
100. OZ
7.96E-D7
TC -99
100. OZ
6.37E-07
TC -99
100. OZ
5.61E-07
TC -99
100. OZ
1000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
9.39E-07
TC -99
100.0Z
8.22E-07
TC -99
100. OZ
6.99E-07
TC -99
100. OZ
5.55E-07
TC -99
100. OZ
4.86E-07
TC -99
100. OZ
1500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
7.10E-07
TC -99
100. OZ
5.88E-07
TC -99
100. OZ
4.58E-07
TC -99
100. OZ
3.98E-07
TC -99
100. OZ
2000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
6.58E-07
TC -99
100. OZ
5.27E-07
TC -99
100. OZ
4.02E-07
TC -99
100. OZ
3.45E-07
TC -99
100. OZ
4000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
N05IE
O.OZ
4.57E-07
TC -99
100. OZ
3.01E-07
TC -99
100. OZ
2.47E-07
TC -99
100. OZ
-------
Table 5.5
Example of Dispersion in Ground voter of a Nucliiie with a Retardation Factor of Ten
(All Doae Rate Values are Relative)
OISIAflCE (meters)
Tim Cyr)
l.OOE+01
2.001*01
5.00E-MJI
l.OQE+02
2.00E+02
5.QOE+02
l.OQE+03
Z.OOE+03
5- ";H+03
l.OOE+04
20.00
0.0
NODE
O.OZ
0.0
KOBE
Q.OX
0.0
HOHE
O.OZ
2.23B-02
SK-126
100. OZ
2.21E-02
SN-126
100. OZ
2.14E-02
SN-126
100. OZ
2.03E-02
SH-126
100.0%
1.82E-OZ
SH-126
100. OZ
1.32E-02
SH-126
100.0Z
7.748-03
SN-126
100. OZ
50.00
0.0
HOHE
0,0!
0.0
HONE
O.OX
0.0
HONE
O.OZ
0.0
NONE
o.oz
0.0
NOHE
O.OZ
1.37E-02
SN-126
100. OZ
1.30B-02
SH-126
100. OZ
1. 17E-02
SH-126
100.01
8.47E-G3
SH-126
100. OZ
4.96E-03
SH-126
100.0Z
100.00
0.0
HOHE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OX
0.0
HONE
O.OZ
0.0
NOHE
O.OZ
9.93B-03
SN-126
100. OZ
9.41E-03
SH-126
100. OZ
8.46E-03
SH-126
100.02
6.13B-03
SH-126
100. OZ
3.59B-03
SN-126
100. OZ
200.00
0.0
HOHE
O.OZ
0.0
NONE
O.OZ
0.0
NOHE
O.OZ
0.0
HOHE
O.OZ
0.0
HOHE
O.OX
0.0
HOME
O.OZ
6.98E-03
SN-126
100.0Z
6.27E-03 •
SH-126
100.02
4.55E-03.
SH-126
100. OZ
2.67B-03
SN-126
100. OZ
500.00
0.0
HOHE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HOHE
O.OZ
0.0
HOHE
O.OZ
0,0
HONE
O.OZ
0.0
NOHE
O.OS
0.0
NONE
O.OZ
3.32E-03
SH-126
100. OZ
1.94E-03
SN-126
100.0Z
750.00
0.0
NOHE
O.OZ
0.0
HONE
O.OX
0.0
NOHE
O.OZ
0.0
HOHE
O.OZ
0.0
MONK
O.OX
0,0
HONE
O.OZ
0.0
NOHE
O.OZ
0.0
NONE
O.OX
3.05E-03
SH-126
100. OZ
1.79E-03
SN-126
100.01
1000.00
0.0
HONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OX
0.0
HONE
O.OX
0.0
NOHE
O.OZ
0.0
NOHE
O.OZ
0.0
NOHE
O.OZ
0.0
NOHE
O.OZ
2.98E-03
SN-126
100. OZ
1.74E-03
SN-126
100. OX
1500.00
0.0
HOHE
O.OZ
0.0
NONE
O.OZ
0,0
NONE
O.OZ
0.0
NOHE
O.OZ
0.0
HONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
NOSE
O.OZ
0.0
HOHE
O.OZ
1.81B-03
SH-126
100.0Z
2000.00
0.0
HONE
o.oz
0.0
NOHE
O.OZ
0.0
HOHE
O.OX
0.0
NONE
0.0%
0.0
HOHE
O.OZ
0.0
NONE
O.OZ
0.0
NOHE
O.OZ
0.0
NONE
O.OZ
0.0
HOHE
O.OZ
1.99E-03
SN-126
100. OZ
4000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0,0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NOHE
O.OZ
0.0
HOHE
O.OZ
0.0
NONE
O.OZ
-------
Table 5.6
Example at Diaperiion in Groundv«ter of < Huclide with « Retardation Factor of One Hundred
(All Doae Hate Values are Relative)
DliftAMCE (aetera)
TIME (yr)
l.OOEi-Ol
2.00E+01
5.00B+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
20.00
0,0
NONE
0.0%
0.0
NONE
0,0%
0.0
NONE
0,0%
0.0
NONE
0.0%
0.0
HOME
0.0%
0.0
RONS
0.0%
4.E8E+01
Att-243
100. OX
3.54E+01
AM- 243
loo. an
2.0QE+01
AM-243
100. 0*
7.70E+QO
AM-243
100.01
50.00
0.0
HONE
0.0*
0.0
HONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
HONE
0.0%
0.0
HONE
O.OX
0,0
NONE
0.0%
0.0
NOHE
0.0%
1.46E+01
AH-243
100.0%
5.62E+00
AM-243
100.0%
100.00
0.0
NOHE
0.0%
0.0
HONE
0.0%
0.0
NOHE
0.0%
0.0
NODE
0,0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
o.o:
0.0
HONE
0.0%
1.31E+01
AM-243
100. OZ
5.04E+00
AM-243
100.0%
200.00
0.0
NONE
0,0%
0.0
HONE
0.0%
0.0
NOME
0.0%
0.0
NONE
0.0%
0.0
HONE
0.0%
0.0
HONE
0.0%
0.0
NOHE
0.0%
0.0
NONE
0.0%
0.0
NOHE
O.OX
5.74E*00
AH-243
100.0%
500.00
0.0
NONE
0.0%
0.0
HONE
0.0%
0.0
NOHE
0.0%
0.0
HONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0!
0,0
NONE
0.0%
0.0
NONE
0.0%
0,0
NONE
0.0%
750.00
0.0
NONE
0.0%
0.0
HONE
0.0%
0.0
NODS
0.0%
0.0
NONE
0.0%
0.0
HONE
0.0%
0.0
NOHE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
HONE
0.0%
0.0
NONE
O.OZ
1000.00
0.0
NONE
0.0%
0.0
BONE
0.0%
0.0
HONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NOHE
0.0%
0.0
NOHE
0.0%
0.0
NONE
O.OZ
1500.00
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
HONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
0.02
0.0
NONE
0.0%
0.0
NONE
0,0%
0.0
NONE
O.OZ
2000.00
0.0
HONE
0.0%
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
HONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
0.01
0.0
NONE
0.0%
0.0
NONE
O.OZ
4000.00
0.0
NONE
O.OZ
0.0
NOHE
O.OX
0.0
HONE
0.0%
0.0
NONE
O.OZ
0.0
NOHE
0.0%
0.0
NOHE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
O.OZ
-------
values at any time decrease fairly slowly with increasing distance. By
several hundred years after drilling, the Tc-99 has spread extensively.
Table 5.6 shows that the slowly moving nuclide Am-243 is much more
restricted. It does not appear in the table for the first 1000 years,
since It takes this long to travel 20 meters; even at 10,000 years, it
has not yet traveled 500 meters. The americium table is characterized
by the large number of zero dose rate values, in contrast to the
technetium table. The movement of Sn-126» given in Table 5.5, is
intermediate betweeen those of technetium and americium.
5.1.1 D1rect hit 'on waste
Table 5.7 gives the results of our base case for a direct hit
drilling release to an aquifer. The event has occurred 1000 years after
the repository is sealed. The shorter-lived nuclides, Sr-90 and Cs-137,
have decayed. Cesium (Cs), iodine (I) and technetium, each with a
retardation factor of 1» move 21 meters in 10 years, and therefore give
the dose rate at location (20 m, 10 yr) in the table. At the 100-year
dose time Sn-126, with a retardation factor of 10, has moved 21 meters
and contributes most of the (20 m, 100 yr) dose rate. The nuclides with
a retardation factor of 1 have moved farther, giving doses at distances
up to 200 meters. At 1000 years after the event, all nuclides have
contaminated parts of the aquifer. Dose rates increase markedly at
1000 years because of the arrival of Ara-241, with a large inventory
and a large DECF, An-241 is dominant at short distances for about
3000 years after the event, then Am-243 becomes the major contributor.
The half-life of Am-243 is longer, hence it does not decay as quickly.
The 10,000-year dose time exhibits an interesting effect. Between
100 and 200 meters, the dose rate rises with distance. This is because
the material at 200 meters was leached out of the canister 500 years
earlier when the inventory was higher. The material at 200 meters has
traveled 9500 years in the aquifer to reach that point. It left the
repository about 500 years after sealing. The material at 100 meters
69
-------
Table 5.7
Dose Equivalent Ratea
TIME (ytj
1.00E+Q1
2.00E+01
5.00E+Q1
i.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00B+03
l.OQE+04
(rem/yr) from Drinking Groundwster Contaminated by Badionuclidea
Released by Borehole Drilling
1000 Years After Repository Sealing
Drill Hie* Waste
DISTANCE (meters)
20.00
1.96E-03
CS-135
5S.5Z
1.96E-03
OS- 135
58.5%
1.95E-03
CS-135
58.6%
2.42E-Q2
SK-126
92. OZ
2.40E-02
SN-126
92. 0%
2.32E-02
SH-126
92.1%
6.25E+02
AM-241
93.1%
1.51E+02
AM-Z41
16.61
2.09E+01
A«-243
95.4%
7.74E-K10
AM-243
99.5%
50.00
0.0
NONE
0.0%
0.0
mm
0,01
1.24E-03
CS-135
58.62
1.23E-03
CS-135
58.71
1.21E-Q3
CS-135
59.0%
1.49E-02
SH-126
92. 2Z
1.41E-02
SN-126
92. /tl
1.2SE-02
SH-126
92. 6t
1.53E+01
AM-243
95. 4Z
5.64E+00
AH-243
99. 6Z
100.00
0.0
HONK
O.OZ
0.0
NONE
O.OZ
8.77E-04
CS-i35
58. 6%
8.70E-04
CS-135
58. 7Z
8.57E-04
OS- 135
59.0%
1.07E-02
SH-126
92 .4%
1.02E-02
SN-126
92. 5Z
9.11E-03
SH-126
92. 8Z
1.37E+01
AM- 243
95. 4X
5.061+00
AM-243
99. 7Z
200.00
0.0
HONE
O.OZ
0.0
HONE
0.0%
0.0
HONE
0.0%
6.18E-04
CS-135
58.7%
6.09E-04
CS-135
59.0%
5.82E-04
CS-135
59.9%
7.52E-03
SN-126
92.82
6.74E-03
SH-126
93.0%
4.861-03
SH-126
93. 6Z
5.73E+00
AH-243
99. 8Z
500.00
0.0
HONE
0.0%
0.0
HODS
O.OZ
0,0
HONK
O.OZ
0.0
RONE
O.OZ
0.0
HOHE
0.0%
3.74E-04
CS-135
59.91
3. ATE -04
CS-135
61. 3Z
3.01E-04
CS-135
64.0%
3.52E-03
SH-126
94.31
2.05E-03
SH-126
94.6%
750.00
0.0
HONE
0.0%
0.0
NONE
0.0%
0.0
NOME
O.OZ
0.0
HONE
O.OX
0.0
NONE
0.0%
3.09E-04
CS-135
59.9%
2.87E-04
CS-135
61.3%
2.4BE-04
CS-135
64. OZ
3.22E-03
SB- 126
94.9%
1. 88B-03
SS-126
95. 3%
1000.00
0.0
HONE
0.0%
0.0
HOHE
0.0%
0.0
HONE
0.0%
0.0
NONE
O.OX
0.0
NONE
0.0%
2.71E-04
OS- 135
59.9%
2.52E-04
CS-135
61.3%
2.18E-04
CS-135
64. OZ
3.12E-03
SH-126
95.4%
1.82E-03
SH-126
95.8%
1500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
HONE
O.OZ
0.0
SONS
0.0%
0.0
HOHE
O.OZ
2.10E-04
CS-135
61.3%
1.82E-04
CS-135
64.0%
1.21E-04
CS-135
71.6%
1.87E-03
SH-126
96.6%
2000.00
0.0
HOHE
0.0%
0.0
NONE
0.0%
0.0
HOHE
0.0%
0.0
NONE
O.OZ
0.0
NOME
0.0%
0.0
mm
0.0%
1.87E-04
CS-135
61.3Z
1.62E-04
CS-135
64.0%
I. 078-04
CS-135
71.6%
2.04E-03
SH-126
97. 2X
4000.00
0.0
HOHE
O.OZ
0.0
NONE
0.0%
0.0
HONE
O.OZ
0,0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
HOHE
0,0%
1.26B-04
CS-135
64. OZ
8.32E-05
CS-135
71.6%
4.43E-05
CS-135
81.4%
-------
has taken about 4750 years to reach that point; it left the repository
about 5250 years after sealing. During the additional 4750 years that
the 100-meter material stayed in the repository, it was subject to
leaching that reduced its inventory by about 35%. The concentration of
nuclide at 200 meters was reduced by about 3CK b> diffusive dilution in
the aquifer while the nuclide traveled from 100 to 200 meters, not
quite enough to make up for the 35% higher concentration at which it
left the repository. This is shown mathematically in equation 4.3a,
where the last factor is:
exp[(-L)(t-te-kx/v)].
Rearranged, this factor becomes:
exp(-Lt) exp(Lt ) exp(+Lkx/v).
The last exponential increases as the distance, x» increases. This
effect can be seen in many locations of Table 5.7 in the later dose
times. This increasing exponential is competing with the diffusion
term, which decreases as the square root of distance. The "x" terms
are:
exp(Lkx/v)
x1/2 "
Table 5.8 shows the results of the direct hit drilling event
occurring 200 years after the repository is sealed. Sr-90 dominates
for the first 200 years. At 1000 years, dose rates increase markedly
as Am-241 reaches the 20-meter distance. The maximum dose in this case
is 2000 rem/yr which occurs at 20 meters and 1000 years; Am-241
contributes 1950 rem/yr. The dose rate from Am-241 in Table 5.7 was
582 rem/yr. The lower value for the 1000-year event is due to
additional radiological decay before the drilling intrusion.
The next two tables, 5.9 and 5.10, show the annual dose rates from
drilling releases 3350 and 7500 years after sealing. Dose rates are
lower than at 1000 years due to radiological decay of the nuclides.
Table 5.9 shows a maximum dose rate of 51 rem/yr, 1000 years after the
drilling, mostly from Am-243. The amount of Am-241, in the 4350 years
71
-------
Table S.8
Ooae Equivalent Rates (reo/yr) from Drinking Groundvater Contaminated by Rsdionuelides
Released by Borehole Drilling
ZOO Years After Repository Sealing
Drill Hits Waste
DISTANCE (meters)
TIHE (yr)
l.OOE+Ol
2.00E+01
5.0QE+01
l.OOE+02
2,OOE-K>2
5.00E+Q2
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
20,00
1.01E+02
SR -90
76. 7Z
7.92E+01
SR -90
76.61
3.86E+01
SR -90
76.02
1.17E+01
SR -90
75.0Z
1.09E+QO
SR -90
71.731
2.42E-02
SH-126
88.72
2.QOE+03
AM-241
97.71
4.27E+02
AM-241
91. 1*
2.46S+01
AM-243
87.3%
8.32S+00
AM-243
99. 5Z
50.00
0.0
HONE
o.oz
0.0
HONE
0.02
2.45E+01
SR -90
76.0%
7.40E+00
SI -90
75. 1Z
6.78E-01
SR -90
73.2%
i.55g-02
SN-126
88. 9Z
l.*2S-02
SB- 126
92. 1%
1.27E-02
SN-126
92.4%
1.79E+01
AM-243
87.3%
6.07E+00
AH-243
99. 6Z
100.00
0.0
HONE
O.OZ
0.0
NONE
O.OZ
1.73E+01
SR -90
76.02
5.24E+00
SR -90
75. 1Z
4.81E-01
SR -90
73. 2%
I. 12E-02
SN-126
89. U
1.03E-02
SH-126
92. 3X
9.19E-03
SN-126
92. 6Z
1.61E+01
AM-243
87. 3%
5.44E+00
AH-243
99. 7Z
200.00
0.0
HONE
O.OX
0.0
HONE
O.OZ
0.0
RONE
O.OZ
3.73E+00
SR -90
75.1%
3.41E-01
SR -90
73.21
8.70E-04
CS-135
40. IX
7.58E-03
SH-126
92.6%
6.79E-03
SN-126
92. 9Z
4.89S-03
SN-126
93. 5Z
6.19E+00
AM-243
99. 8Z
300.00
0.0
NONE
0.02
0.0
NONE
0.02
0.0
HONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
5.58S-04
CS-135
40. 1Z
3.61E-04
CS-135
59. OZ
3.11E-04
CS-135
61.81
3.54E-03
SH-126
94. 2*
2.06E-03
SN-126
94. 8Z
750.00
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
o.ot
4.61E-04
CS-135
40. 1Z
2.98E-04
CS-135
59.0%
2.57E-04
C3-135
61.81
3.24S-03
SH-126
94. 8Z
1.89E-03
SN-126
95. 3Z
1000.00
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
mm
O.OZ
4.04E-04
CS-135
40. 1Z
2.61E-04
CS-135
59.0%
2.26E-04
CS-135
61. 8Z
3.14E-03
SH-126
95. 3Z
1.83E-03
SH-126
95. 7Z
1500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
SONS
O.OZ
0.0
NONE
0.0%
0.0
HONB
O.OZ
0.0
HONE
O.OZ
2.192-04
CS-135
59.0%
1.89E-04
CS-135
61. 8%
1.24E-04
CS-135
69. 6%
1.88E-03
SH-126
96. 5Z
2000.00
0.0
HONE
O.OS
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
o.oz
0.0
HONS
O.OZ
0.0
NONE
O.OZ
1.94E-04
CS-135
58.9%
1.67E-04
CS-135
61.81
1.101-04
CS-135
69. 6%
2.06E-03
SN-126
97. 2Z
4000.00
0.0
HONE
0.02
0.0
NONE
0.0%
0.0
NONE
O.OZ
0,0
NONE
O.OZ
0.0
RONE
O.Of
0.0
HONE
O.OZ
0.0
HONE
O.OZ
1.30E-B4
CS-135
61.7%
8.55E-05
CS-135
69.7%
4.51E-05
CS-135
80. 1Z
-------
Table 5.9
Dose Equivalent Rates (reo/yr) from Drinking Grounduater Contaminated by
Radionuclidea Releaaed by Borehole Drilling
3350 Years After Repository Sealing
Drill Hita Waste
DISTANCE (meters)
TIME (yr)
l.OOE+01
2.00E+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+U3
l.OOE+04
20.00
1.77E-03
CS-135
65. OZ
1.76E-03
CS-135
65. IX
1.76E-03
CS-135
65. 1Z
2.37E-02
SN-126
92. 6Z
2.34E-02
SN-126
92.71
2.27E-02
SN-126
92. 7Z
5.13E+01
AM-243
67.51
3.20E+01
AM-243
89.5X
1.62E+01
AM-243
99.61
6.26E+00
AM-243
99.4Z
50.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
1.11E-03
CS-135
65. 1Z
1. 10E-03
CS-135
65. 3Z
1.09E-03
CS-135
65. 5Z
1.45E-02
SN-126
92". 8%
1.38E-02
SN-126
92. 9Z
1.23E-02
SN-126
93. 1Z
1.18E+01
AM-243
99.61
4.56E+00
AM-243
99. 5Z
100.00
0.0
NONE
O.OZ
0.0
HONE
O.OZ
7.88E-04
CS-135
65. 1Z
7.83E-04
CS-135
65. 3Z
7.72E-04
CS-135
65.5%
1.05E-02
SN-126
93. OZ
9.95E-03
SN-126
93. 1Z
8.92E-03
SN-126
93. 2Z
1.06E+01
AM-243
99. 7Z
4.09E+00
AH-243
99. 7Z
200.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
5.56E-04
CS-135
65.3Z
5.48E-04
CS-135
65. 5Z
5.26E-04
CS-135
66. 3 J
7.36E-03
SN-126
93. 3Z
6.60E-03
SN-126
93. 5Z
4.77E-03
SN-126
93. 9Z
4.65E+00
AM-243
99. 8Z
500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
3.37E-04
CS-135
66.3*
3.15E-04
CS-135
67.61
2.75E-04
CS-135
70. 1Z
3.45E-03
SN-126
94. 6Z
2.01E-03
SN-126
95. OZ
750.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
2.79E-04
CS-135
66. 3Z
2.60E-04
CS-135
67. 6Z
2.27E-04
CS-135
70. 1Z
3.16E-03
SN-126
95. 1Z
1.84E-03
SN-126
95. 4Z
1000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.02
0.0
NONE
O.OZ
2.44E-04
CS-135
66.3*
2.28E-04
CS-135
67. 6Z
1.99E-04
CS-135
70. 1Z
3.06E-03
SN-126
95. 6Z
1.79E-03
SN-126
95. 9Z
1500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
1.91E-04
CS-135
67.61
1.66E-04
CS-135
70. 1Z
1.12E-04
CS-135
76.71
1.84E-03
SN-126
96. 7Z
2000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0,0
NONE
O.OZ
1.69E-04
CS-135
67.61
1.47E-04
CS-135
70. 1Z
9.97E-05
CS-135
76. 7Z
2.01E-03
SN-126
97. 3Z
4000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
1.15E-04
CS-135
70. 1Z
7.76E-05
CS-135
76. 7Z
4.24E-05
CS-135
85. OZ
-------
Table 5.10
Dose Equivalent Rates (ren/yr) froa Drinking Groundw«ter Contaminated by Radionuclide*
Released by Borehole Drilling
7500 Years After Repository Sealing
Drill Hits Waste
DISTANCE (meters)
TIME (yr)
l.OOE+01
2.00E+01
S.OOE+Ol
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E-K53
5.00E+03
l.OOE+04
20.00
1.53E-03
OS- 135
75,1%
1.53S-03
CS-135
75. IX
1.S2E-03
CS-135
15.lt
2.28S-02
SB- 126
93.4%
2.26E-02
SH-126
93.4%
2.19E-02
SH-126
93.4%
2.38E+01
AM-243
99.7%
1.97E+01
AM-243
99.7%
1.11E+01
AM-243
99.6%
4.31B+00
AM-243
99,2%
50.00
0.0
HOME
0.0%
0.0
HOME
0.0%
9.63E-04
CS-135
75.1%
9.57S-04
CS-135
75.3%
9.45E-04
CS-135
75.51
1.40E-02
SH-126
93.5%
1.33B-02
SH-126
93.6%
1. 19E-02
SH-126
93.7%
8.1U+00
AM-243
99.7%
3. 14E+00
AM-243
99.3%
100.00
0.0
HOSE
0.0%
0.0
HOSE
0.0%
6.82E-04
CS-13S
75.1%
6.782-04
CS-135
75.3%
6.69E-04
CS-135
75.5%
1.011-02
SH-126
93.6%
9.60E-03
SH-126
93.7%
8.62E-03
SH-126
93.8%
7.27E+00
AM-243
99.8%
2.81E+00
AM-243
99.5%
200.00
0.0
NONE
0.0%
0.0
HONE
0.0%
0.0
NONE
0.0%
4.82S-04
CS-135
75.3%
4.76S-04
CS-135
75. 5S
4.58B-04
CS-135
76.1%
7.10E-03
SH-126
93.9%
6.37E-03
SH-126
94.0%
4.611-03
SH-126
94.3%
3.19E+00
AM-243
99.8%
500.00
0.0
HONE
0.0%
0.0
HONE
O.OZ
0.0
NONE
0.0%
0.0
HONE
0.0%
0.0
HONE
0.0%
2.948-04
CS-135
76.1%
2.761-04
CS-135
77.1%
2.43E-04
CS-135
79.0%
3.34E-03
SN-126
94.9%
1.96B-03
SH-126
95.1%
750.00
0.0
mm
O.OZ
0.0
NONE
0.0%
0.0
HONE
0.0%
0.0
RONE
0.0%
9.0
HONE
0.0%
2.43E-04
CS-135
76.1%
2.28S-04
CS-135
77.1%
2.01E-04
CS-135
79,0%
3.06E-03
SN-126
95.4%
1.79E-03
SN-126
95.61
1000.00
0.0
NONE
O.OZ
0.0
NONE
o.oz
0.0
RONS
O.OZ
0.0
NONE
0.0%
0.0
HONE
0.0%
2.131-04
CS-ISS
76.1%
2.00E-04
CS-13S
77.1%
1.76E-04
CS-135
79.0%
2.97E-03
SM-126
95.9%
1.74E-03
SN-126
96.0%
1500.00
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
0.0%
0.0
MORE
0.0%
1.67E-04
CS-135
77.1%
1.47E-04
CS-135
79.0%
1.03E-04
CS-135
83.9%
1.79E-03
SN-126
96.7%
2000.00
0.0
NONE
0.0%
0.0
HOME
O.OZ
0.0
NONE
O.OZ
0.0
HONE
0.0%
0.0
NONE
0.0%
0.0
HOME
O.OZ
1.4SS-04
CS-135
77.1%
1.31E-04
CS-135
79.0%
9.11JJ-05
CS-135
83.9%
1.95K-03
SB- 126
97.4%
4000.00
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
HONE
0.0%
0.0
NOHE
O.OZ
1.02B-04
CS-135
79.0%
7.08E-05
CS-135
84.0%
4.02E-05
CS-135
89.7%
-------
since repository sealing, has decreased by a factor of about 700. In
Table 5.10 the highest dose rate is 24 rem/yr, 1000 years after
drilling, almost entirely from Am-243.
Table 5.11 shows the area contaminated by this direct hit drilling
release 200, 1000, 3350, and 7500 years after sealing. Contaminated
areas occur before 1000 years only for the 200-year drilling event;
Sr-90 is the chief contributor. For later drilling events, areas
contaminated to give dose rates above 0.5 rera/yr appear 1000 years
after drilling as americium nuclides arrive. These areas increase and
reach a maximum 10,000 years after drilling. The largest areas
contaminated to give more than 0.5 rem/yr do not differ much for the
four drilling event times, ranging from 6.2 ha (62,000 square meters)
for the 200-year event to 5.3 ha for the 7500-year drilling event. For
all four cases, the maximum area contaminated is a little less than one
percent of the 800-hectare area of the repository. Areas contaminated
above 5 rem/yr also appear 1,000 years after drilling and reach their
largest extent 5,000 or 10,000 years after drilling, after which they
decrease rapidly. For the 200-year and 1000-year drilling events, the
maximum areas contaminated to give more than 5 rem/yr are 1.7 and
1.3 ha, respectively, at 10,000 years after the drilling. For the
3350-year and 7500-year drilling events, the maximum areas contaminated
are one ha and 0.75 ha, respectively, at 5000 years after the
drilling. Small areas contaminated more severely, above 50 and
500 rem/yr, also appear at 1000 years after drilling but decrease
rapidly as the nuclides diffuse to lower concentrations.
5.1.2 Brine pocket
The results and tables discussed to this point assume that a drill
hits the waste directly. Even if the drill does not hit waste, it may
hit one of several brine pockets in a salt repository which result from
water leaks through the shaft seals (SmC 82, ADL 79). The brine pocket
in the reference case is assumed be in contact with waste from two
75
-------
Table 5.11
Area (ha*) of the Aquifer Contaminated
Above the Specified Dose Rate Levels Following a
Direct Drilling Hit on Waste
Dose Levels (rem/yr)
0.5 5.0 50 500
Time After
Drill (yr)
10
20
50
100
200
500
1,000
2,000
5,000
10,000
200 years after sealing
0.14
0.13
1.3
2.8
0.26
0
0.36
0.32
2.1
6.2
0.10
0.10
0.80
0.45
0
0
0.30
0.26
1.3
1.7
0.05
0.04
0
0
0
0
0.24
0.18
0
0
0
0
0
0
0
0
0.15
0
0
0
Dose Levels (rem/yr)
0.5 5.0 50 500
1000 years after sealing
0
0
0
0
0
0
0.33
0.30
2.1
6.1
0
0
0
0
0
0
0.27
0.23
1.2
1.3
0
0
0
0
0
0
0.20
0.13
0
0
0
0
0
0
0
0
0.06
0
0
0
3350 years after ssaling
7500 years after sealing
10
20
50
100
200
500
1,000
2,000
5,000
10,000
0
0
0
0
0
0
0.27
0.25
2.0
5.8
0
0
0
0
0
0
0.19
0.17
1.0
0.06
0
0
0
0
0
0
0.02
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0.24
0.24
1.9
5.3
0
0
0
0
0
0
0.16
0.14
0.75
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
*1 hectare (ha) = 104 square meters
76
-------
canisters and is 0.06 m3 in volume (SmC 82). Table 5.12 gives the
annual dose rates from drilling into a brine pocket 1000 years afer
repository sealing. The highest dose rate is 1150 rem/yr at 20 meters
and 1000 years after the drilling. This is almost twice the value of
H25 rem/yr for the direct hit case (Table 5.7) All annual dose rates
in Table 5.12 are approximately twice those in Table 5.7, reflecting
the situation when the brine pocket is in contact with waste from two
canisters. The annual dose rates from drilling into a brine pocket
200 years, 3350 years, and 7500 years after repository sealing
^fables 5.13, 5.14, and 5.15) are approximately twice those in the
corresponding direct hit cases in Tables 5.8, 5.9, and 5.10. The same
nuclides are significant and the discussion in Section 5.1.1 applies
here as well. Table 5.16 shows the groundwater areas contaminated
after drilling into a brine pocket. The general spread of
contamination, which is such that the less heavily contaminated areas
become larger up to 10,000 years after drilling, is similar to that for
the direct hit case (Table 5.11). It is noteworthy that the areas
contaminated by drilling into a brine pocket are only slightly larger
than those contaminated by a direct hit, although the annual dose rates
at a given point are almost twice as large.
5.1.3 Granite tank
If a drill penetrates into a granite repository, there will be a
release of nuclides even if the drill does not hit waste. Water that
has filled the void volume of 2 x 10 ro In the repository becomes
contaminated by leaching and dissolving of the waste after the
canisters fail at 500 years after repository sealing. The earliest
event time we considered was 500 years after sealing (ADL 79). The
releases from any earlier drilling would be zero until the canisters
fail at 500 years.
Table 5.17 gives the annual dose rates resulting from drilling into
the granite tank 1000 years after sealing. Cs-135 and Sn-126 give
small doses in the first 1000 years. At 1000 years, Am-241 appears at
20 meters as the major contributor to a dose rate of 1800 rem/yr.
77
-------
Table 5.12
Dote Equivalent Rates (reo/yr) froa Drinking Groundwater Contaminated by Radionuelidea
Released by Borehole Drilling in BEDDED SALT
1000 Tear* After Repository Sealing
Drill Hits Repository Water
PISTANCE (metera)
TIME (yr)
l.OOEtQl
2.00E+01
5.00E+01
l.OOE+02
2.QOE+02
5.00E+02
l.QOE+03
2.00E-HJ3
5.00E+03
1.00E+Q4
20.00
3.57E-03
CS-135
58.6Z
3.59E-03
CS-135
58.6Z
3.58E-03
CS-135
58.71
4.44E-02
SH-126
92.0%
4.39E-02
SH-126
92. OX
4.25E-02
SN-126
92.12
1.15E+03
AM-241
93. IX
2.78E+02
AM-241
76.61
3.80E+01
AM-243
95.51
1.40E+01
AM-243
99. 71
50,00
0.0
HOME
0.0%
0.0
HONE
0.0%
2.26E-03
CS-135
58.7%
2.25E-03
CS-135
58.8Z
2.211-03
CS-135
59.1%
2.73E-02
SN-126
92.21
2.50E-02
SH-126
92 .ill
2.30E-02
SH-126
92.6%
2.79E-MJI
AM-243
95.51
1.04E+01
AM-243
99.71
I 'JO. 00
0.0
HONE
o.oz
0.0
NONE
O.OZ
1.60E-03
CS-135
58. 7%
1.59E-03
CS-135
58.8%
1.57E-03
CS-135
59.1%
1.97B-02
SN-126
92.4%
1.87E-02
SH-126
92. 5Z
1.67E-02
SH-126
92. 7Z
2.5H+01
AM-243
95.5Z
9.1SE+00
AM-243
99.8*
200.00
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
HONE
O.OZ
1. 13E-03
CS-135
58. BZ
1.11E-03
CS-135
59.11
1.07E-03
CS-135
60.0Z
1.38E-02
SN-126
92.8%
1.24E-02
SH-126
93.0%
8.821-03
SH-126
93.6%
1.05E+01
AM-243
99. 9Z
500.00
0.0
NONE
O.OZ
0.0
NOHE
O.OZ
0.0
NONE
0.0%
0.0
HONE
0.0%
0.0
HONE
O.OZ
6.85B-04
CS-135
60.0%
6.35E-04
CS-135
61.4%
5.48E-04
CS-135
64.1*
6.44E-03
SN-126
94 .4Z
3.77E-03
SN-126
94.9%
750.00
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NOUS
O.OZ
5.65E-04
CS-135
60.0%
5.26E-04
CS-135
61.4%
4.54E-04
CS-135
64.1%
5.90E-03
SN-126
95.0%
3.41E-03
SN-126
95.3%
1000.00
0.0
NONE
0.0%
0.0
HONE
O.OZ
0.0
HONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
4.951-04
CS-135
60.0Z
4.61E-04
CS-135
61.4%
3.97E-04
CS-135
64.1%
5.72E-03
SN-126
95.4%
3.30E-03
SN-126
95. 8%
1500.00
0.0
HONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
HOHE
O.OZ
0.0
HONE
O.OZ
3.85E-04
CS-135
61.4%
3.33E-04
CS-135
64.1%
2.191-04
CS-135
71. 7Z
3.44E-03
SN-126
96.6%
2000.00
0.0
KOHE
0.0!
0.0
HONE
0.0%
0.0
HONE
O.OZ
0.0
NOHE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
0.0%
3.42E-04
CS-135
61. 4Z
2.96E-04
CS-135
64.1%
1.94E-04
CS-135
71.7%
3.74E-03
SN-126
97.2%
4000.00
0.0
HONE
O.OZ
0.0
NOHE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
HOHE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
2.30E-04
CS-135
64. 1Z
1.52B-04
CS-135
71. 7Z
8.06E-05
CS-135
81. 7Z
-------
Tsble 5.L3
Dose Equivalent Races (rem/yir) from Drinking 6round»«t*r Contaminated by Radionuclides
Released by Borehole Drilling in BEDDED SALT
200 Years After Repository Sealing
Drill Hies Repository Water
DISTANCE (metera)
TIMS (yr)
l.OOE+01
2.00E+01
5.00E+01
i,OOE*02
2.00E+02
S.OOE+02
l.OOE+03
2,0(8*03
5.00E+03
1.002*04
20.00
2.00E+02
SR -90
76. n
1.57E+02
SR -90
76.6%
7.68E+01
SR -90
76.01
2.32E+01
SR -90
75. OS
2.17E+00
SR -90
71. 11
4.81E-02
SH-126
88.71
3.97E+03
AM-241
97. n
8.49E+Q2
AM-241
91. U
4.87E+01
AM-243
87,4%
1.631401
AH-243
99.71
50.00
0.0
NOME
0,0%
0.0
NONE
0.0%
4.86B+01
SR -90
76. OX
1.47E+01
SR -90
75.11
1.35E+00
SR -90
73.21
3.08E-02
SH-126
88.91
2.81E-02
SH-126
92. IX
2.52E-02
SB- 126
92.41
3.55E+01
AM-243
87 .4%
1.21E+01
AH-243
99.81
100.00
0.0
NONE
0.02
0.0
NONE
0.0%
3.45B+01
SR -90
76.01
1.04E+01
SR -90
75. IX
9.54E-01
SR -90
73.2%
2.23E-02
SN-126
89. U
2.04E-02
SN-126
92.3%
1.82B-02
SH-126
92.5%
3.19E+01
AH-243
87.41
l.06E*Oi
AM-243
99.81
200.00
0.0
NONE
O.OX
0.0
NONE
0.0%
0.0
NONE
0.0%
7.40E+00
SR -90
75. U
6.78E-01
SR -90
73.2%
1.73E-03
CS-135
40.2%
1.51E-02
SN-126
92.6%
1.35E-02
SH-126
92.8%
9.68E-03
SN-126
93.51
1.23B+01
AM-243
99.9%
500.00
0.0
NONE
0.0%
0.0
NONE
0.01
0.0
NONE
0.0%
0.0
HONE
0.0%
0.0
NONE
O.OZ
1. 11E-03
CS-135
40.1%
7.15E-04
CS-135
59.1%
6.17E-04
CS-135
61.9%
7.01E-03
SN-126
9*. 2%
4.1 11-03
SH-126
94.8%
750.00
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
0.0%
9.13E-04
CS-135
40.1%
5.91E-04
CS-135
59.1%
5.10E-04
CS-135
51.91
6.43E-03
SN-126
94.9%
3.71E-03
SN-126
95.3%
1000.00
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.0%
8.031-04
CS-135
40.1%
5.18E-04
CS-135
59.1%
4.47E-04
CS-135
61.9%
6.23E-03
SN-126
95.3Z
3.59E-03
SN-126
95.7%
1500.00
0.0.
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
HONE
0.0%
4.32E-04
CS-135
59.1%
3.74E-04
CS-135
61.9%
2.43E-04
CS-135
69.8%
3.75E-03
SH-126
96.6%
2000.00
0.0
NONE
0.0%
0,0
HONE
0.0%
0.0
NONE
0.0%
0.0
HONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
3.85E-04
CS-135
59.1%
3.32E-04
CS-135
61. 9Z
2.17E-04
CS-135
69.8%
4.07E-03
SH-126
97.2%
4000.00
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
HONE
O.OZ
2.58E-04
CS-135
61.9%
1.69E-04
CS-135
69.8Z
8.88E-05
CS-135
80.3%
-------
CO
o
fable 5.14
Dote Equivalent Race* (rem/yr) [roa Drinking Groundtrater Contaminated by H«dlonuelU*«
Released by Borehole Drilling in BEDDED SALT
3350 Veare After Repository Sealing
Drill Hit« Repository Hater
DISTANCE (meters)
TIME (yr)
l.OOB+01
2.00E+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
Z.OOE+03
5.00E+03
l.OOK+04
20.00
2.47E-03
OS- 135
65. 1*
2.57E-03
CS-135
65. U
2.55E-03
CS-135
65.21
3.44E-02
SH-126
92. 7Z
3.42E-Q2
SH-126
92.71
3.3UE-02
SH-126
92. 8Z
7.42E+01
AM-243
47. 5Z
4.5SE+01
AH-243
89.5Z
Z.34E+01
AM-243
99.6%
S.96E+00
AM-243
99.6Z
50.00
0.0
HONE
O.OX
0.0
HONE
o.oz
1.62E-03
CS-135
65. 2Z
1.61E-03
CS-135
65.31
1.59E-03
CS-135
65.61
2.10E-02
SH-128
92,8}
2.00E-02
SH-126
93. 01
1.79E-02
SB- 126
93. 2%
1.711*01
AM-243
99. 7Z
6.63E+00
AM-243
99. 6Z
100.00
0.0
HONE
O.OZ
0.0
HONE
O.OZ
1.15E-03
CS-135
65.22
1.14E-Q3
CS-135
65.31
1. 12E-03
CS-135
65.61
1.53E-02
SH-126
92. 9Z
1.441-02
SH-126
93. OX
1.29E-02
SH-126
93. 3Z
1.54E+01
AM-243
99. 7Z
5.84E+00
AM-243
99.7%
200.00
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
HONE
O.OZ
8.08E-04
CS-135
65.31
8.01E-04
CS-135
65.6%
7.68R-D4
CS-135
66.41
1.06E-02
SH-126
93.42
9.41S-03
SH-126
93 .4%
6.87E-03
SN-126
93.9Z
6.76E+00
AM-243
99.81
500. OO
0.0
NONE
0.0%
D.Q
HOME
O.OZ
0.0
HONE
O.OX
0.0
NONE
O.OZ
0.0
NOME
O.OZ
4.87S-04
CS-135
66.41
4.57E-04
CS-135
67. Ti
3.97E-04
CS-135
70. 1Z
4.98E-03
SH-126
94. 6Z
2.93E-03
SH-126
95.0%
750.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OX
0.0
NONE
O.OX
0.0
NONE
O.OZ
4.02E-04
CS-135
66. 4Z
3.76E-04
CS-135
67. n
3.24E-04
CS-135
70. 1Z
4.54E-03
SM-126
95. 2Z
2.65E-03
SH-126
95. 5t
1000.00
0.0
HOHE
O.OZ
0.0
HOHE
O.OZ
0.0
HONK
O.OX
0.0
NONE
O.OZ
0.0
HOHE
O.OZ
3.55E-04
CS-135
66.4X
3.28E-04
CS-135
67. 7Z
2.88E-04
CS-135
70.11
4.44E-03
SH-126
95, 6X
2.56E-03
SH-126
95. 9X
1500,00
0.0
HONE
O.OZ
0.0
HONE
O.OZ
0.0
HOHE
O.OZ
0.0
HOHE
O.OX
0.0
HOME
O.OX
0.0
NONE
O.OZ
2.75E-04
CS-135
67. 7X
2.38E-04
CS-135
70. IX
1.61E-04
CS-135
76.8Z
2.65E-03
SN-126
96.7%
2000.00
0.0
HONE
O.OZ
0.0
NODE
O.OZ
0.0
HONE
O.OZ
0.0
HOHE
O.OX
0.0
NONE
O.OZ
0.0
HONE
O.OZ
2.44S-04
CS-135
67. 7Z
2.10E-04
CS-13S
70. IX
1. 448-04
CS-135
76.8X
2.92E-03
SH-126
97. 3X
4000.00
0.0
HON3
O.OX
0.0
NONE
O.OX
0.0
HOHE
O.OZ
0.0
HONE
O.OZ
0.0
HOHE
O.OZ
0.0
HOME
o.ot
0.0
HOHE
O.OZ
1.66E-04
CS-135
70. IX
1.10E-04
GS-135
76. 8X
6.11E-05
CS-135
85. U
-------
Table 5,15
00
TIMS (yr)
1.QOE+Q1
2.00E+01
5.00E+01
l.OOE+02
2.00E+U2
5.00E+02
l.OOE+03
2.00E+Q3
5.00E+03
l.OOE+04
Dose Equivalent Rates (rem/yr) from Drinking Groundwater Contaminated by Radionuclides
Releaaed by Borehole Drilling in BEDDED SALT
7500 Yeara After Repository Sealing
Drill Hits Repository Hater
DISTANCE (meters)
20,00
1.35E-03
CS-135
75. OZ
1.45E-03
CS-135
75.135
1.44E-03
CS-135
75.1%
2.16E-02
SN-126
93 .4Z
2.14E-02
SK-126
93. 4Z
2.08E-02
SN-126
93,5%
2.27E+01
AH-243
99.61
1.86E+01
AH-243
99. 7Z
1.06E+01
AH-243
99. 6Z
4.08E-HH)
AH-243
99.11
50.00
0.0
HONE
0.0%
0,0
NONE
O.OZ
9.0BE-04
CS-135
75.11
9.10E-04
CS-135
75.2Z
7.45E-04
CS-135
75. 4Z
1.31E-02
SN-126
95.0*
1.27E-02
SH-126
93:6Z
1. 14B-02
SN-126
93, 7*
7.73E+00
AM-243
99. 7*
3.01E+DO
AM-243
99.3%
100.00
0.0
NONE
o.oz
0.0
NONE
O.OZ
6.48E-04
CS-135
75. IX
6.45B-04
CS-135
75, 2Z
6.36E-04
CS-135
75. 5%
9.71E-03
SN-126
93, 7Z
9.00E-03
SN-126
95. 1Z
8.25E-03
SN-126
93. m
6.92B+00
AM-243
99. 8Z
2.66E+00
AM-243
99. 5Z
200.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
4.57E-04
CS-135
75. 2Z
4.52E-04
CS-135
75. 5Z
4.35E-04
CS-135
76. n
6.77E-03
SN-126
94. OZ
5.96E-03
SM-126
95. 3Z
4.40E-03
S8-126
94. 2Z
3.04E+00
AM-243
99. 7Z
500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
2.79E-04
CS-135
76. 1Z
2.65E-04
CS-135
77. 1Z
2.33E-04
CS-135
79, OZ
3.18E-03
SH-126
94. 9Z
1.88E-03
SN-126
95. IZ
750.00
0.0
NONE
O.OZ
0,0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
2.301-04
CS-135
76, IZ
2.14E-04
CS-135
77. IZ
1.55E-04
CS-135
79.0Z
2.45E-03
SN-126
94. 6Z
1.69E-03
SN-126
95,5%
1000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0,0
HONE
O.OZ
0.0
NONE
O.OZ
2.04E-Q4
CS-135
76. IZ
1.90E-04
CS-135
77. IZ
1.69E-04
CS-135
79. OZ
2.83E-03
SH-126
95. 9Z
1.64E-03
SN-126
96.0%
1500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NOSE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
1.59E-04
CS-135
77. IZ
1.39E-04
CS-135
79. OZ
9.73E-05
CS-135
83.91
1.70E-03
SN-126
96. 8Z
2000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0,0
NONE
O.OZ
1.41E-04
CS-135
77. IZ
1.24E-04
CS-135
79, OZ
8.6BE-05
CS-135
83.91
1.86E-03
SN-126
97.4Z
4000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
o.oz
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
9.68E-05
CS-135
79. OZ
6.68E-05
CS-135
84. OZ
3.83E-05
CS-13S
89.61
-------
Table 5.16
Area (ha*) of the Aquifer Contaminated
Above the Specified Dose Rate Levels
Following Drilling into a Brine Pocket
Dose Levels (rem/yr)
0.5 5 50 500
Dose Levels (rem/yr)
0,5 5 50 500
Time
After
Drill tyr)
1,
2,
5,
10,
10
20
50
100
200
500
000
000
000
000
200 years after sealing
0
0
1
3
1
0
0
2
7
.14
.14
.4
.2
.40
0
.3?
.34
.3
.0
0.11
0.11
0.96
1.5
0
0
0.32
0.28
1.6
3.7
0.07
0.06
0.08
0
0
0
0.26
0.21
0
0
0
0
0
0
0
0
0.18
0.09
0
0
1000 years
0
0
0
0
0
0
0.
0.
2.
6.
34
31
31
8
0
0
0
0
0
0
0.29
0.25
1.5
3.3
after sealing
0
0
0
0
0
0
0.22
0.16
0
0
0
0
0
0
0
0
0.11
0
0
0
3350 years after sealing 7500 years after sealing
10
20
50
100
200
500
1,000
2,000
5,000
10,000
0
0
0
0
0
0
0.28
0.26
2.1
6.3
0
0
0
0
0
0
0.20
0.18
1.2
2.1
0
0
0
0
0
0
0.08
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0.24
0.24
1.9
5.2
0
0
0
0
0
0
0.15
0.14
0.71
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
*1 hectare (ha) = 10^ square meters
82
-------
Tsfels 5.17
oo
(yr)
l.OOE+01
Z.OOE+Ql
5.00K+01
i.OQE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
Dose Equivalent Rates (ren/yr) from Drinking Groundvater Contaminated by Radionuclides
Released by Borehole Drilling in GRANITE
1000 Years After Repoaitory Sealing
Drill Hits Repository Hater
DISTANCE (meters)
20.00
5.40B-03
CS-135
58,6%
5.47E-03
CS-135
58.7Z
5.66E-03
CS-135
58.8%
6.78E-02
SB- 126
91.2%
7.57E-02
SH-125
91,4%
9.34E-02
SN-126
91,8%
1.83E+03
AM-241
93.1%
7.93E+02
AM-241
76,6%
1.37E+Q2
AH-243
95.5%
2.96E+01
AH-243
99.9%
50.00
0.0
NONE
0.0%
0.0
NONE
O.OX
3.52E-03
CS-135
58,8%
3.72E-03
CS-135
58.91
4.061-03
CS-135
59.2%
5.461-02
SN-126
91.2%
6.75B-02
SN-126
91.9%
7.64E-02
SN-126
92,5%
9.96E-1-01
AH-243
95.6%
2.64E+01
AM-243
99. 9Z
100.00
0.0
NONE
0.0%
0.0
NONE
0.0%
2.42E-03
CS-135
58.8%
2.56E-03
CS-135
58.9%
2.82E-03
CS-135
59.2%
3.16E-02
SH-126
89.3%
4.43B-02
SN-126
91.3%
5.34E-02
SN-126
92,4%
4.67E+01
AM-243
99.6%
3.06E+01
AH-243
99.9%
200.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OX
1.71E-03
CS-135
58. 9Z
1.908-03
CS-135
59.2%
2.33E-03
CS-135
60. 1Z
2.32E-02
SN-126
88,3%
3.58E-02
SH-126
91.9%
3.16E-02
SH-126
93.9%
2.40E+01
AM-243
99.9%
500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HOHE
O.OX
0.0
HOHE
O.OZ
0.0
HONE
O.OZ
1.351-03
CS-135
60.1%
1.651-03
CS-135
61. 5Z
I.B1E-03
CS-135
64.2%
2.29E-02
SH-126
94.6%
9.48E-03
SH-125
96.2%
750.00
0.0
HONE
O.OZ
0.0
HONE
O.OZ
0.0
HOHE
O.OZ
0.0
HONE
0.0%
0.0
NONE
0.0%
1.001-03
CS-135
60.1%
1.30E-03
CS-135
61.5%
1.47B-03
CS-135
64.2%
1. 851-02
SH-126
94.4%
9.98E-03
SB- 126
96.9%
1000.00
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
mm
0.0%
0.0
NONE
0.0%
0.0
NONE
O.OZ
7.68E-04
CS-135
60. OZ
1.08E-03
CS-135
61.5%
1.27E-03
CS-135
64.2%
1.15E-02
SN-126
92.0%
1.09E-02
SN-126
97.5%
1500.00
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
HOHE
O.OZ
0.0
NONE
O.OZ
7.75E-04
CS-135
61.5Z
1.011-03
CS-135
64.2%
7.77E-04
CS-135
71. 8Z
1.22E-02
SN-126
98.11
2000.00
0.0
RONE
0.0%
0.0
HONE
0.0%
0.0
HOHE
O.OZ
0.0
SOHE
0.0%
0.0
HONE
0.0%
0.0
NONE
O.OZ
5.46B-04
CS-135
61. 5%
8.44E-Q4
CS-135
64.2%
6.96E-04
CS-135
71.8%
8.53E-03
SB- 126
97.4%
4000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HOHE
0.0%
0.0
NONE
O.OZ
0.0
RONE
0.0%
0.0
NONE
0.0%
0.0
NONE
O.OZ
3.89E-04
CS-135
64.2%
5.49B-04
CS-135
71,8%
1.94E-04
CS-135
81.9%
-------
Sn-126 and Cs-135 have traveled further from the release site. The
maximum dose occurs at the 1000-year dose time and the major con-
tributor is Am-241,
When drilling occurs 500 years after repository sealing (Table 5.18)
there are some small annual dose rates before 1000 years later, the
major contributors being strontium-90 (Sr-90) for the first 100 years
and Sn-126 after that. The Sr-90 contribution is much less than it was
for the direct hit and brine pocket cases at 200 years because most of
this nuclide (and also most of the Cs-137) has decayed in the
approximately 17 half-lives since repository sealing. The ftm-241
appears at 20 meters and 1000 years as the major contributor to a dose
rate of 480 rem/yr. This dose rate is much smaller than the corres-
ponding one for the 1000-year drilling event because there has been
much less time for Am-241 to be leached from the waste into the repos-
itory water. In both cases, the Am-241 and -243 has taken 950 years to
travel 20 meters, and therefore left the repository 50 years after the
drilling. In the 500-year drilling event, the total time for leaching
was 50 years; in the 1000-year drilling event, it was 550 years. The
additional leaching of Am-241 has more than compensated for the decay
of that nuclide during the 500 years.
Tables 5.19 and 5.20 give the annual dose rates from drilling into
the granite tank 3350 and 7500 years after sealing. The highest dose
rates are lower than those for 1000 years, 260 and 66 rem/yr,
respectively. This reduction is caused by the decay of Am-241. The
additional leaching of Am-243 into the tank before the drilling event
keeps the dose rate from becoming very small. The behavior of nuclides
after a few thousand years post-event are similar for all four drilling
times.
The maximum contamination from Am-241 occurs from drilling
1140 years after the repository is sealed. We calculated this maximum
time by setting the derivative (aC/st) in equation 4.11 equal to zero.
For all events after 1140 years, the size of all contaminated areas
will fall as the concentration of Am-241 drops, because Am-241 is the
largest contributor.
84
-------
CO
TIME (yr)
l.OOE+01
Z.OOE+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E-K13
l.OOE+04
Table 5.18
Equivalent Rates (rem/yr) from Drinking Groundvater Contaminated by Radionuclides
Released by Borehole Drilling in GRANITE
500 Years After Repository Sealing
Drill Hits Repository Hater
DISTANCE (ranters)
20.00
3.21E-04
SR -90
68.42
5.48E-03
SR -90
68.72
1.04E-02
SR -90
66.02
8.62E-03
SR -90
51.42
2.12E-02
SN-126
82.21
5.86E-02
SN-126
90,9%
4.81E+O2
AM-241
96.52
1.30E+03
AM-241
87. OJ
1.59E+02
AM-243
91.42
3.50E-KJ1
AU-243
99.92
50.00
0.0
NONE
0.02
0.0
NONE
0.02
4.32E-03
SR -90
66.02
4. 1SB-03
SR -90
57. IX
2.Z4E-Q3
CS-135
40. 22
2. 768-02
SN-126
88.02
5.46E-02
SN-126
91. 2Z
7.39E-02
SN-126
92.22
i.UE+02
AK-243
91.41
3.09E+01
AM-243
99.92
100.00
0.0
HONE
0.02
0.0
NONE
0.02
2.85E-04
SR -90
65.62
2.07E-03
SR -90
57.12
1.40E-03
CS-135
40.22
4.16E-03
SH-126
45.72
3 . 16E-02
SN-126
89.32
5.05E-02
SN-126
92.02
2.25E+01
AM-243
99.12
3.50E+01
AM-243
99.92
200.00
0.0
NONE
0.02
0.0
NOHE
0.02
0.0
NONE
0.02
1.40E-04
SR -SO
56.52
7.07E-04
CS-135
40.12
1.48E-03
CS-135
58.6%
4.95E-03
SN-126
52.9%
3.16E-02
SN-126
90.92
3.39E-02
SH-126
93.72
1.68E+01
AM-243
99.9%
500.00
0,0
HONE
0.02
0,0
HONE
0.02
0,0
HONE
0.02
0.0
NONE
0.02
0.0
NOHE
0.02
6.74E-04
CS-135
53.62
1.35E-03
CS-135
60. U
1.7BE-03
CS-135
62.92
2.35E-02
SH-126
94.12
1.07E-02
SH-126
96.12
750.00
0.0
NONE
0.02
0.0
RONE
O.OZ
0.0
NOHE
0,0!
0.0
NOHE
O.OZ
0.0
NOHE
O.OZ
3.31E-04
CS-135
58.51
l.OOE-03
CS-135
60.12
L.43E-03
CS-135
62.91
1.74E-02
SN-126
93.52
1.11E-02
SH-IZ6
96.82
1000.00
0.0
NOHE
O.OZ
0.0
NOHE
D.02
0.0
NOHE
0.02
0.0
NOHE
0.01
0.0
NONE
0.02
5.34E-05
CS-135
57.9%
7.68E-04
CS-135
60.02
1.21E-03
CS-135
62.91
5.88E-03
SN-126
82.92
1.19E-02
SN-126
97.41
1500.00
0.0
NONE
0.02
0.0
NOHE
O.OZ
0.0
NONE
0.02
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
4.07E-04
CS-135
60.02
9.40E-04
CS-135
62.92
8.46E-04
CS-135
70.6Z
1.25E-02
SH-126
97. 8Z
2000.00
0.0
NOHE
O.OZ
0.0
HONE
O.OZ
0.0
NOHE
O.OZ
0.0
NOHE
O.OZ
0.0
HONE
0.02
0.0
NOHE
0.02
7.UE-Q5
CS-135
59.72
7.52E-04
CS-135
62.92
7 . 54E-04
CS-135
70. 6Z
5.82E-D3
SN-125
95.72
4000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
0.0%
0.0
NONE
O.OZ
9.27E-05
CS-135
62.72
5 . 78E-04
CS-135
70.62
2.20E-04
CS-135
81. OZ
-------
Table 5.19
CO
(yr)
l.OOE+01
2.00E+01
5.0QE+01
1.00E+O2
2.00E+02
S.OOE+02
i.OOE+03
2.00E+03
5.00E+03
l.OOE+04
Dose Equivalent Rate* (cem/yt) from Drinking Groundwater Contaminated by Radionuclidci
Released by Borehole Drilling in GRANITE
3350 Years After Repository Sealing
Brill Hit* Repository Hater
DISTANCE (metern)
20.00
8.95E-03
OS- 135
65,2%
S.94E-03
CS-135
65. 21
8. 928-03
CS-135
65. 3X
l.ZOE-01
SN-126
32.61
l.ZOE-01
SH-126
92.62
1. 18E-01
SN-126
92.7Z
2.61E+02
AM-243
57.5%
1.67E+Q2
AM-243
89.61
6.95E-»01
AH-243
99.8%
1.31E+01
AH-243
99.93!
50.00
0.0
HOME
0.0%
0.0
NOME
O.OZ
5.651-03
CS-135
65.31
5.PE-03
CS-135
6S.4Z
5.58E-03
CS-135
65.71
7.50B-02
SH-126
92.81
7.21E-02
SN-126
92.91
6.35E-02
SH-126
93,21
5.79E+01
AM-243
99.8%
l.ZOEtOl
AM-243
99.91
100.00
0.0
NONE
O.OZ
0.0
NONE
0.0%
4.00S-03
CS-135
65.31
3.98E-03
OS- 135
65.41
3.95E-03
CS-135
es. n
5.36S-02
SH-126
92, 8Z
5.191-02
SH-126
93. OZ
4.63E-02
SB- 126
93.41
5.46E+01
AM-243
99. n
1.52E+01
AM-243
99.91 •
200.00
0.0
KOHK
0.01
0.0
NONE
0.0%
0.0
HO US
O.OZ
2.82E-03
CS-135
65.43
2.80E-03
CS-135
65.7%
2.72E-03
08-135
66.5%
3.761-02
SH-126
93.22
3.45E-02
SH-126
93. 7Z
2.03E-02
SN-126
94. 5Z
2.42E+01
AM-243
100,01
500.00
0.0
HONE
O.OZ
0.0
HOWE
O.OZ
0.0
mm
O.OZ
0.0
HOME
O.OZ
0.0
NONE
0.0%
1.74E-03
CS-135
66.5%
l.b4E-03
CS-135
67,8%
1.41S-03
CS-135
70. 3%
1.57E-02
SH-126
95.6%
5.24E-03
SH-126
96.4Z
750.00
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONK
0.0%
1.43S-03
CS-135
66.51
1.361-03
CS-135
67.8Z
1. 17E-03
CS-135
70.3Z
1.63E-02
SH-126
96.21
5.72E-03
SH-125
97.2%
1000.00
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
1.24E-03
CS-135
66.5%
1.19E-03
CS-135
67. 8Z
1.03E-03
CS-135
70. 3Z
1.57E-02
SH-126
96, 5Z
6.53E-03
SN-126
97.8Z
1500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NOSE
O.OZ
0.0
HONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
9.82E-04
CS-135
67.8%
8.67E-04
CS-135
70.3Z
4.68E-04
CS-135
77.0%
8.68E-03
SN-126
98.6Z
2000.00
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0,0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
O.OZ
8.59E-04
CS-135
67.81
7.71E-M
CS-135
70.3%
4.27E-04
CS-135
7?. 01
1.03E-02
SN-126
98.9Z
4000.00
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
HONI
O.OZ
0.0
HONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
0.0%
5.85E-04
CS-135
TO. 3%
3.64E-04
CS-135
77.0%
1.03E-04
CS-135
85.5%
-------
Table 5.20
oo
TIHE (yr)
l.OOE+01
2.0QE+01
5.00E*01
l.OOE+02
2.00E+02
5.00E+02
I.OOE+03
2.ODE+03
5.00B+03
l.OOE+04
Dose Equivalent Raced ( rem/yr) from Drinking Groundwater Contaminated by Kadionuclldea
fteleaeed by Borehole Drilling in GRANITE
7500 Years After Repository Sealing
Drill Hits Repository Hater
DISTANCE (mater«)
20.00
4.27E-03
CS-135
75. 2%
4.24E-03
OS- 135
75.31
4.23E-03
CS-135
75,3%
6.39E-02
SK-126
93.51
6.25E-02
SN-126
93,5%
5.84E-02
SH-126
93. 5 %
6.64E+01
AM-243
99.8%
4.861+01
AH-243
99.9%
1.77E+01
AW-243
99.9%
2.85E+00
AM-243
99.8%
50.00
0.0
HONE
0.0%
0.0
NONE
0.0%
2.68E-03
CS-135
75.3%
2.65E-03
CS-135
75.4%
2.59E-03
CS-135
75.6%
3.80E-02
SN-126
93.7%
3.39E-02
SN-126
93.7%
2.67E-02
SH-126
93.9%
1.61E+01
AM-243
99.9Z
Z.70E+00
AH-243
99.91
100.00
0.0
NONE
0.0%
0.0
NOME
0.0%
1.91B-03
CS-135
75.3%
1.88B-03
CS-135
75.4%
1.84E-03
CS-135
75.6%
2.82B-02
SH-126
93.9%
2.52E-02
- SN-126
94.01
1.99B-02
SH-126
94.21
1.98E+01
AM-243
100.0%
3.66E+00
AM-243
99.9%
200.00
0.0
NONE
O.OJ
0.0
NONE
0.0%
0.0
HONE
o.os
1.35E-03
CS-135
75.4%
1.31B-03
CS-135
75.6%
1.221-03
CS-135
76.31
1.97E-02
SN-126
94.5%
1.5«E-02
SN-126
94.7%
7.28E-03
SN-126
95.0%
8.45E+00
AM-243
10Q.OX
500.00
0,0
HOME
O.OZ
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
HOHE
0.0%
0.0
NOHE
0.0%
7.97E-04
CS-135
76.3%
7.04E-04
CS-135
77.3%
5.44E-04
CS-135
79.2%
6.53E-03
SS-126
96.3%
1.66E-03
SN-126
96.6%
750,00
0.0
NONE
0.0%
0.0
NODE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
6.68E-04
CS-135
76.3%
5.90E-04
CS-135
77.3%
4.57E-04
CS-135
79.2%
7.05S-03
SK-126
97.11
1.B7E-03
SN-126
97.5%
1000.00
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
HONE
o.o*
0.0
mm
0.0%
0.0
NONE
0.01
5.93E-04
CS-135
76.3%
5.25B-04
CS-135
77.3%
4.07E-04
CS-135
79.2%
7.94E-03
SN-126
97.7%
2.22E-03
SH-126
98.11
1500.00
0.0
NOHE
O.OZ
0.0
NONE
0.0%
0.0
NOME
O.OS
0.0
NONE
0.0%
0.0
HOHE
O.OZ
0.0
NONE
0.0%
4.52E-04
CS-135
77,31
3.52E-04
CS-135
79.2%
1.S7E-04
CS-135
84.3%
3.35E-03
SH-126
98.9%
2000.00
0.0
HOHE
0.0%
0.0
HONE
0.0%
0.0
NONE
0,0%
0.0
NOME
0.0%
0.0
NONE
0.0%
0.0
HONE
0.0%
4.12E-04
CS-135
77.3%
3.22E-04
CS-135
79.2%
1.44E-04
CS-135
84.3%
5.07E-03
SN-126
99.3%
4000,00
0.0
HONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
0.0%
0,0
NONE
0.0%
0.0
HONE
0.0%
Z.81E-04
CS-135 .
79.2%
1.30E-04
CS-135
84.3%
3.16E-05
GS-135
90.2%
-------
Table 5.21 shows the extent of aquifer contamination after drilling
into the granite tank. The general pattern of the spread of
contamination at dose rates above 0.5 and 5 rem/yr is similar to that
seen for the direct hit and brine pocket cases, although the
contaminated areas are somewhat larger, and contamination for the
500-year event is markedly less than for the 1000-year event. Areas
contaminated to the 50- and 500-rem/yr levels are somewhat larger and
the contamination is more persistent than for the other two cases.
5.2 Releasesto theAquifer due to Faulting
For faulting events (Section 4.2), we used a different mathematical
description and coordinate system. We selected the positive x-axis in
the direction of aquifer flow, which is parallel to the assigned fault
direction. The origin is at one end of the repository and
x = 4000 meters at the other end. The mathematical description is given
in Chapter 4 where the event is modeled by integrating releases from a
line source, equivalent to a large number of borehole drilling events.
We assumed that the fault line intersects wastes from one row of
canisters and ruptures all of the canisters if they are still intact in
that row. The wastes then leach or dissolve into the groundwater.
5.2.1 Fault hits waste
For this case, the same pathway characteristics were assigned to
both the bedded salt and granite repositories. Table 5.22 gives the
annual dose rates at the preselected distances and times for a faulting
event at 1000 years after repository sealing that directly affects the
waste from a row of canisters. Sn-126 is the predominant nuclide until
50 years after the faulting because the americium nuclides take 50 years
to travel one meter. Am-241 is dominant from 50 to 2000 years. From
5000 to 10,000 years, Am-243 is the most important nuclide. The highest
dose rate is about 600 rem/yr at 500 years. After 500 years, the dose
rates decline as the decay of the nuclides outweighs the contributions
from waste further away from the dose point. Only the two americium
isotopes give substantial doses. Doses from americium increase for
88
-------
Table 5.21
Area of the Aquifer Contaminated
Above the Specified Dose Ra^.e Levels
Following Drilling into the Granite Tank
Dose Limits (rem/yr)
0.5 5 50 500
Time After
Drill (yr)
1
1,
2,
5,
0,
0-500
000
000
000
000
200
0
0.
0.
2.
7.
years
32
35
4
5
0
0.
0.
T
1 *
4.
after
26
29
6
6
0
0
0
0
,
*
.
0
sealing
19
22
38
0
0
0.
0
0
12
Dose Limits (rem/yr)
0.5 5 50 500
1000 years after sealing
0
0.36
0.34
2.5
7.8
0
0.30
0.28
1.8
5.0
0
0.24
0.21
0.36
0
0
0.14
0.08
0
0
3350 years aftersealing
0-500
1,000
2,000
5,000
10,000
0
0.31
0.30
2.5
7.5
0
0.25
0.23
1.8
4.6
0
0.16
0.14
0.39
0
0
0
0
0
0
7500 years after sealing
0
0.27
0.27
2.2
6.2
0
0.20
0.19
1.3
2.0
0
0.06
0
0
0
0
0
0
0
0
*1 hectare (ha) = 10^ square meters
89
-------
Table 5.22
Dose Equivalent Ratea (rera/yr) from Drinking Groundwater Contaminated by Radionuclidefl
Released by Fault Moveaent
1000 Years After Repository Sealing
Haste Directly Affected
DISTANCE (metera)
IIME (yr)
l.OOE+01
2.00E+Q1
5.QOE+01
l.OOE+02
2.00E+02
5.00E+Q2
l.OOE+03
£ .
2.00E+03
5.00E+03
l.OOE+04
ZO.OO
S.30E-03
SN-126
42, 2%
8.28E-03
SN-126
63.1!
1.38B+01
AM-241
97.31
2.32E+02
AH-241
97.2%
4.61E+02
AM-241
96,8!
6.LOE+02
AM-241
95.11
4.37E+Q2
AM-241
90,2%
1. 16E-MJ2
AM-241
- 67.7%
2.77E+01
AM-243
48.9%
1.28E+01
AH-243
40.8%
50.00
5.40E-03
SH-126
41.51
1.0 12-02
SN-126
51.9%
1.38E+Q1
AM-241
97. 3Z
2.32E+02
AH-241
97.2%
4.61E+Q2
AM-241
96.8%
6.10E+02
AM-241
95.1%
4.50E+02
AM-241
90.2%
1.77E+02
AM-241
67.6%
4.64E+01
AM-243
48.6%
2.15E+Q1
AH-Z43
40. 5Z
100.00
S.40E-03
SN-126
41.5%
1.01E-02
SN-126
51.9%
1.38E+01
AM-241
97.3%
2.32E+02
AH-241
97.2%
4.61E+02
AM-241
96.8%
6.10E+02
AH-241
95.1%
4.50E+02
AM-241
90.2%
1.77E+02
AH-241
67.6%
6.42E*01
AM-243
48.2%
2.99E+01
AM-243
40.0%
200.00
5.40E-03
SN-126
41.5%
1.01E-02
SN-126
51.9%
1.38E+01
AM-241
97.3%
2.32E+02
AM-241
97.2%
4.61S+02
AM-241
96.8%
6.10E+02
AH-241
95.lt
4. 50E+02
AM-241
90.2%
1.77E+02
AH-241
67.6%
6. 5SE*01
AM-243
48.2%
3.88E+01
AH-243
39.1%
500,00
5.40E-03
SN-126
41.5%
1.01E-02
SN-126
51.9%
1.38E-MH
AM-241
97.3%
2.321+02
AM-241
97.2%
4.61B+02
AH-241
96.8%
6.10E+02
AH-241
95. IS
4.50E+02
AM-241
90.2%
1.77E+0?
AM-241
67.0%
6.SSE+01
AH-243
48.2%
3.94E+01
AH-243
39.1%
750.00
5.40E-03
SH-126
41.5%
1.01E-02
SN-126
51.9%
1.38E+01
AM-241
97.3%
2.32E+02
AM-241
97.2%
4.61E+Q2
AM-241
96.8%
6.10E+02
AM-241
95.1%
4.501+02
AH-241
90.2%
1.77B+02
AM-241
67.6%
6.56B+01
AH-243
48.2%
3.94E+01
AH-243
39.0%
1000.00
5.40E-03
SN-126
41.5%
1.01E-02
SN-126
51.9%
1.38E+01
AM-241
97.3%
2.32E+02
AH-241
97.2%
4.61E+02
AM-241
96.8%
6.10E+02
AM-241
95.1%
4.50S1-02
AM-241
90.2%
1.77E+02
AM-241
67.6%
6.56E+01
AM-243
48.2%
3.94E+01
AM-243
39.0%
1500.00
5.40E-03
SN-126
41.5%
1.01E-02
SN-126
51.9%
1.38E+01
AH-241
97.3%
2.32E+02
AH-241
97.2%
4.61E+02
AH-241
96.8%
6.10E+02
AM-241
95.1%
4.50S+02
AH-241
90.2%
1.77E+02
AH-241
67.6%
6.56E+Q1
AM-243
48.2%
3.94E+01
AH-243
39.0%
2000.00
5.40E-03
SN-126
41.5%
1.01E-02
SN-126
51.9%
1.38E+01
AH-241
97,3%
2.32E+02
AM-241
97.2%
4.61E+02
AM-241
96.8%
6.10E+02
AM-241
95.1%
4.50E+02
AM-241
90.2%
1.77E+02
AH-241
67.6%
6.56E-KH
AM-243
48.2%
3.94E*01
AM-243
39.0%
4000.00
5.40E-03
SH-126
41.5%
1.01E-02
SN-126
51.9%
1.38B+01
AM-241
97.3%
2.32E+02
AH-241
97.2%
4.61E+02
AM-241
96.8%
6.10E+02
AH-241
95,1%
4 . 50E*02
AM-241
90.2%
1,77E*02
AM-241
67.6%
6.56E+01
AH-243
48.1%
3.95E+01
AM-243
39.0%
-------
the first 500 years, representing the ability of these nuclides to
reach the dose points from greater distances.
From 50 to 500 years, the annual dose rates are the same over the
entire length of the repository. The annual dose rates at each point
represent contributions from a very short distance because the
important Ara-241 travels only 10,5 meters in 500 years. After this
time, the points close to the upstream (or upgradient) end of the
repository show slightly lower dose rates. For example, at 5000 years,
the annual dose rates at 20, 50 and 100 meters are slightly less than
those at longer distances. In 5000 years, americium travels 105
meters. As a result, all the annual dose rates from 200 to 4000 meters
are the same because they represent contributions from as far away as
105 meters. The annual dose rates at 20, 50 and 100 meters are lower
because there is no waste beyond the edge of the repository that would
be a source for these points at this time.
Tables 5.23, 5.24, and 5.25 give the annual dose rates from
faulting at 200, 3350, and 7500 years after repository sealing. The
dose rates in this case decrease for later faulting; for example, the
highest dose rates at 4000 meters are 1970, 600, 36, and 21 rem/yr for
faulting at 200, 1000, 3350, and 7500 years, respectively. The
200-year event dose rates are dominated by Sr-90 for 50 years. The
maximum doses from the Sr-90 occur at (4000 m, 20 yr), 74 rem/yr. The
Am-241 takes between 50 and 100 years to reach the aquifer.
Table 5.24 shows the same important nuclides at 3350 years as at
1000 years. For the 7500-year event, Am-243 is the only important
americium isotope because the Am-241 has decayed. Other contaminants
at 7500 years are the same as for the other event times. No area
tables are calculated for the faulting releases.
5.2.2 Faulting through a granite tank or brine pocket
In this scenario, only the granite repository is examined because
the initial release from the granite tank would be greater than from a
brine pocket because of its greater volume and also later in time the
91
-------
5.23
Dsoe Equivalent Racei limm/ff) fton Drinking Croundw»t*r Cont»rain«teil by Rudionuclidei
Releaied by Fault Movenent
200 Y««rt After Repository Sealing
Waste Directly AfEceted
DISTANCE (attera)
TIME (yr)
i.OOE+01
2.00E+QI
5.00E+01
l.OOE+02
2.0QB+02
5.00B+02
l.OOE+03
2.00E+03
5.QOE+03
l.OQE+04
20.00
7.80B+01
SR -90
76.7%
6.L4E+01
SR -90
75.51
7.56E+01
AM-241
59. n
7.738+02
AM-241
91. TS,
1.51E+03
AM-241
98.8:
1.98E+03
AH-241
98.41
1.37E+03
AM-241
96.7%
3.03E+02
AM-241
87. OX
3.02E+01
AM-243
48.2?
1.351+01
AM-243
41.51
50.00
8.05E+01
SR -90
76.71
9.71E+QI
SR -90
76.51
9.81E+01
AM-241
46.0%
7.80E+Q2
AM-241
95.91
1.51E+03
AM-241
98.81
1.98E+03
AM-241
98. 4Z
1.41E+03
AH-241
96.71
4.62E+02
AM-241
87.02
5.Q5E+01
AM-243
48.02
2.27E+01
AM-243
41.2%
100.00
8.05E+01
SR -90
76.71
9.71E+01
SR -90
76. 5%
1.23R+02
SR -90
47,92
7.88B+02
AH-241
95.91
1.52E+03
AH-241
98.71
1.98E+03
AH-241
98.4Z
1.41K+03
AM-241
96.71
4.62E+02
AH-241
87. OX
6.99S+01
AM-243
47.7%
3.15E+01
AH-243
40. n
200.00
B.05E+01
SR -90
76.71
9.71E+01
SR -90
76.51
1.25E+02
SR -90
48.31
7.981+02
AH-241
94. n
1.52S+03
AH-241
98. 11
1.98E+03
AH-241
98.42
1.41E+03
AH-241
96.71
4.62E+02
AH-241
87.01
7.13E+01
AM-243
47.6%
4.09B+01
AJ1-243
39. n
500.00
8.05E+01
SR -90
76.71
9.712+01
SR -90
76.51
1.258+02
SR -90
43.31
7.99B+02
AM-241
94.61
1.52E+03
AM-241
98. 61
1.98E+03
AM-241
98 .41
1.41E+03
AM-241
96. n
4.62E+02
AH-241
87.01
7.13E+01
AM-243
47.61
4.16E+01
AH-243
39. 8 X
750.00
8.05E+01
St -90
76.71
9.71E+01
SR -90
76. 5X
1.25E+02
SR -90
48.3%
7.99E+02
AH-241
94.6%
1.52E+03
AH-241
98.61
1.98E+03
AM-241
98.4Z
1.41E+03
AM-241
96.72
4.62E+02
AH-241
87.02
7.13 '01
AM-243
47,6%
4.16E+01
AM-243
39.82
1000.00
8.05E+01
SR -90
76. 7*
9.71E+01
SR -90
76,52
1.25E+02
SR -90
48.3%
7.99E+02
AH-241
94.6%
1.52E+03
AM-241
98.6%
1.98E+03
AM-241
98. 4X
1.41E+03
AM-241
96.72
4.62S+02
AH-241
87.02
7.14E+01
AM-243
47.6%
4.16E+01
AM-243
39.82
1500.00
8.05E+01
SR -90
76.71
9.71B+01
SR -90
76.52
1.251+02
SR -90
48.32
7.99E+02
AM-241
94.62.
1.521+03
AH-241
98.62
1.9SE+03
AM-241
98.42
1.41E+03
AM-241
96.7%
4.62E+02
AH-241
87.02
7.14E+01
AM-243
47.62
4.16B+01
AM-243
39.81
2000.00
8.05E+01
SR -90
76. n
4.71E+01
SR -90
76.52
1.25E+02
SR -90
48.32
7.99B+02
AH-241
94.62
1.52E+03
AM-241
98.62
1.98E+03
AM-Z41
98.42
1.41E+03
AH-241
96.72
4.62E+02
AH-241
87.02
7.148+01
AM-243
47.62
4.16E+01
AH-243
39,82
4000.00
8.05E+01
SR -90
76.72
9.71E+01
SR -90
76.52
1.25E+02
SR -90
48.32
7.99E+02
AM-241
94.62
1.52E+03
AB-241
98.62
1.98E+03
AM-241
98.42
1.418+03
AM-241
96.71
4.62E+02
AM-241
87.02
7.14E+01
AM-243
47.62
4.16B+01
AM-243
39.8%
-------
10
OJ
Table 5.24
Oase Equivalent Rate* (rea/yr) from Drinking Groundwater Contaminated by Radiormcliden
Released by Fault Hovement
3350 Year* After Repository Sealing
Waste Directly Affected
DISTANCE (meters)
TIME
-------
10
Table 5.25
Dose Equivalent Kates (ren/yr) from Drinking Groundwuter Contaminated by Radionuclides
Released by Fault Movenent
7500 ?e«r« After Repository Sealing
Haste Directly Affected
DISTANCE (metera)
TIME
-------
bedded salt would tend to heal itself and greatly reduce or close the
pathway. Table 5.26 gives the annual dose rates at preselected times
and distances for a fault into the granite tank at 1000 years. The
migration of the nuclides, as well as the dominant ones, are the same in
this case as they were for the direct hit case (Section 5.2.1).
However, the dose rates are much higher in this case; they are the
highest found among all the reference cases in this report. The highest
dose rate is 340,000 rem/yr, 100 years after the event. Tables 5.27,
5.28 and 5.29 give the annual dose rates for faulting at 200, 3350, and
7500 years. For faulting at 200 years, the highest dose rate is
200,000 rem/yr, 500 years after the event; it is 110,000 rem/yr for
faulting at 3350 years, and 98,000 rem/yr for faulting at 7500 years.
The highest annual dose rate in the last two cases, as in the 1000-year
faulting event, occurs 100 years after the event. There are no area
tables associated with this scenario. The Am-241 appears at 50 years
because the model treats it as uniformly distributed along the fault
line. The release is integrated from 1 to 4000 meters rather than 0 to
4000 meters, in order to avoid the isolated singularity at x = 0. The
result is a delay in dose time, the time by which the nuclide must
travel the 1.0 meter distance.
5.3. Release to the Land Surface
5.3.1 Direct hit on waste
As in the release to aquifers, this release mode takes place as the
result of a drilling event. A fraction (0.15 for our base case) of the
waste in a canister is carried to the surface, and is subsequently
dispersed into the atmosphere by resuspension (SmC 82; ADL 79). The
nuclides are considered to be in an insoluble form, which gives higher
lung doses. The release to the land surface is characterized by the
fact that the largest dose rates always occur closest to the release
(20 meters in the tables). The largest doses are always recorded at the
earliest times. As dose times increase, the doses fall as the nuclide
95
-------
VO
TIME (yr)
l.OOE+Ol
2.00E+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
1.001+03
2.00E+03
5.00E+03
l.OOE+04
Table 5.26
Dose Equivalent Kates (rem/yr) from Drinking Groundwater Contaminated by Radionucliries
Released by Fault Movement in GRANITE
1000 Years After Repository Sealing
Eepository Hater Affected
DISIAKCE (metf-riQ
20.00
3.75S+01
m-U6
53.3%
2.53E+01
SN-126
88.02
1.67E+05
AM-241
95.4%
3.41E+OS
AM-241
95 .11
2.57E+05
AM-241
94.41
1. 75E+05
AM-241
91.61
7.64E+04
AM-241
84.2%
2.30E+04
AM-241
55.8*
6.14E+03
AM-243
36.0!
2.60E+03
PU-239
36.8%
50.00
3.90E+01
SN-126
51.8%
3.64E+01
SH-126
61.02
1.67B+05
AM-241
95.4%
3.41E+05
AM-241
95, 1Z
2.S7E+05
AM-241
94.41
1.75E+05
AM-241
91.61
1.06E+05
AM-241
84.22
4.41E+04
AM-241
55.8%
1. 131+04
AM-243
36.0%
4.81E+03
PU-239
36.81
100.00
3.90S+01
SH-126
51.8%
3.64E+01
SN-126
61.0%
1.67E+05
AM-241
95.4%
3.41E+05
AM-241
95.1%
2.57E+05
AM-241
94.4%
1.758*05
AM-241
91.6%
1.06E-MJ5
AH-241
84.2%
4.41E+04
AM-241
55.8%
1.84E+04
AM-243
36.0%
7.78E+03
FU-239
36.8%
200.00
3.90E+01
SH-126
51.8%
3.64E+01
SM-126
61.0%
1.67E+05
AM-241
95.4%
3.41E+Q5
AM-241
95. 11
2.57E+05
AM-241
94. 41
1.7SB+Q5
AM-241
91.6%
1.06E+05
AH-241
84.2%
6.41E+04
AM-241
55.8%
2.0SE404
AM-243
36.0%
1.38E+04
TO-239
36.8%
500.00
3.90E+01
SH-126
51.8%
3.64B+01
SH-126
61.0%
1.67E+05
AM-241
95.4%
3.41E+05
AM-241
95.1%
2.57E-1-05
AM-241
94.4%
1. 75E+05
AM-241
91. 61
1.06E+05
AM-241
84.21
4.41E+04
AM-241
55.8%
2.05E+04
AM-243
36.0%
1. 511+04
PU-239
36.8%
750.00
3.90S+01
SH-126
51.8%
3. 641+01
SH-126
61.0%
U67E+05
AM-241
95.4%
3.41E+05
AM-241
95.1%
2.57E+05
AM-241
94.4%
1.75E+05
AM-241
91.6%
1.06E+05
AH-241
84.2%
4.41E+04
AM-241
55.8%
2.05E+04
AM-243
35.9%
1.51E+04
PU-239
36.81
1000.00
3.90E+01
SH-126
51.8%
3.64E+01
SN-126
61.0%
1.67E+05
AM-241
95.4%
3.41E+05
AM-241
95.1%
2.57E+05
AM-241
94.4%
1. 75E+05
AM-241
91.6%
1.06E+05
AH-241
84.2%
4.41E+04
AM-241
55.8%
2.051+04
AM-243
35.5%
1.S1E+04
PU-239
36.8%
1500.00
3.90E+01
SN-126
51.8%
3.64E+01
SN-126
61.0%
1.67E+05
AM-241
95.4%
3.41E+05
AM-241
95.1%
2.57E+05
AM-241
94.4%
1. 75E+05
AM-241
91.6%
1.06S+05
AM-241
84.2%
4.41E+04
AM-241
55.8%
2.051+04
AH-243
35.9%
1.5 IE +04
PU-239
36.8%
2000.00
3.90E+01
SH-126
51.8%
3.64E+01
SH-126
61.0%
1.67E+05
AM-241
95.4%
3.411+05
AM-241
95.1%
2.57E+05
AM-241
94.4%
1.75E+05
AM-241
91.6%
1.06E+05
AM-241
84.2%
4.41E+04
AM-241
55.8%
2.05E+04
AM-243
35.9%
1.5 IE +04
PU-239
36.8%
4000.00
3.90E+01
SH-126
51.8%
3.64E+01
SH-126
61.0%
1.67E+05
AM-241
95.4%
3.41E+05
AM-241
95.1%
2.57E+05
AH-241
94.4%
1.75E+05
AM-241
91.6%
1.06E+05
AH-241
84.2%
4.41E+04
AM-241
55.8%
2.05E+04
AH-243
35.9%
1.52E+04
PU-239
36.7%
-------
Table 5.27
Dose Equivalent Rate* (reoi/yr) from Drinking Grcundwater Contaminated by Radionuclideg
Released by Fault Movement in GRANITE
200 Years After Repository Sealing
Repository Hater Affected
DISTANCE (oeter«)
TIKE (yr)
l.OOE+Qi
2.00B+01
5.0QE+01
l.OOE+02
2,001+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.OOS+04
20.00
6.57E+00
SR -90
66.3%
8.31E+00
SR -90
61.8%
9.2QE+02
AM-241
97.01
7.19E+04
AM-241
97,5%
1.54E+05
AM-241
97.21
2.12E+05
AM-241
95. n
1.57E+05
AM-241
91,62
3.98S+04
AM-241
72.11
6.81E+Q3
AM-243
35.7%
2.83B+03
PU-239
36.1%
50.00
6.58E+00
SR -90
66. 1%
1.11E+01
SR -90
63.0%
9.23E+02
AM-241
96,71
7.19B+04
AM-241
97. 5%
1.54E+05
AH-241
97.2%
2.12E+05
AM-241
95.7%
1.59E+Q5
AM-241
91,6%
6.50E+04
AM-241
72.1%
1.26E+04
AM-243
35.7%
5.22E+03
PU-239
36.1%
100.00
6.5BE+00
SR -90
66.1%
l.llB+01
SR -90
63.0%
9.26E+02
AM-241
96.4%
7.19E+04
AM-241
97.5%
1.54E+05
AM-241
97.2%
2.12E+05
AK-241
95,7%
1.59E+05
AM-241
91.6%
6.50E+04
AM-241
72.1%
2.035*04
AM-243
35. 7Z
8.45E+03
PU-239
36.1%
200.00
6.58E+00
SR -90
66.1%
1.11E+01
SR -90
63.0%
9.26B+02
AM-241
96.4%
7.19E+04
AM-241
97.5%
1.54E+05
AM-241
97.2%
2.12E+05
AM-241
95.7%
1.59E+05
AM-241
91.6%
6,50S*04
AM-241
72.1%
2.10E+04
AM-243
35.7%
1.50E+04
FU-239
36.1%
500.00
6.58E+00
SR -90
66.1%
1.11E+01
SR -90
63.0%
9.26E+02
AM-241
96.4%
7.19E+04
AM-241
97.5%
1.54E+05
AM-241
97,2%
2.121+05
AM-241
95.7%
1.59E+05
AM-241
91.6%
6.51E+04
AM-241
72.1%
2.10B+04
AM-243
35.7%
1.57E+04
PU-239
36.1%
750.00
6.58E+00
SR -90
66.1%
1.11E+01
SR -90
63.0%
9.26E+02
AM-241
96.4%
7.19E+04
AK-241
97.5%
1.54E+05
AM-241
97.2%
2.12E+05
AH-241
95.7%
1.59E+05
AM-241
91.6%
6.51E+04
AM-241
72.1%
2.11E+04
AH-243
35.7%
1.57E+04
PtI-239
36.1%
1000.00
6.58E+00
SR -90
66.1%
1.11E+01
SR -90
63.0%
9.26E+02
AM-241
96.4%
7.19E+04
AM-241
97. 5t
1.54B+05
AM-241
97.2%
2.12E+05
AK-241
95.7%
1.59E+05
AM-241
91,6%
6.51E+04
AH-241
72.1%
2.11E+04
AM-243
35.7%
I. 57E+04
PU-239
36.1%
1500.00
6.58E-KJO
SR -90
66,1%
1.11E+01
SR -90
63,0%
9.26E+02
AM-241
96.4%
7.19E+04
AM-241
97.5%
1.54S+05
AM-141
97. 2S
2. 12E+05
AM-241
95.7%
1.59E+05
AM-241
91.6%
6. 511+04
AH-241
72.1%
2.11E+04
AM-243
35.7%
1.57E+04
PO-239
36.1%
2000.00
6.58E+00
SR -90
66.1%
1.11S+01
SR -90
63.0%
9.26B+02
AM-241
96.4%
7.19E+04
AM-241
97.5%
1.54E+05
AM-241
97.2%
2.12E+05
AH-241
95.7%
1.59E+05
AM-241
91.6%
6.51E+04
AM-241
72.lt
2.11E+04
AH-243
35.7%
1.58E+04
PU-239
36.1%
4000.00
6.58E+00
SR -90
66.1%
1.118+01
SR -90
63.0%
9.26E+02
AM-241
96.4% ,
7.19E+04
AM-241
97.5%
1.54E+05
AM-241
97.2%
2.12E+05
AM-241
95.7%
1.59E+05
AM-241
91.6%
6.51E+04
AM-241
72.1%
2.11E+04
AH-243
35.6%
1.58E+04
PO-239
36.1%
-------
Table 5,28
ID
00
TIMS (yr)
l.OOE+01
2.00E+01
5.00E+01
l.QOE+02
2.00E+Q2
5.QOE+02
l.OOE+03
2.00E+03
S.OOE+03
l.OOE+04
Doae Equivalent Rate* (rem/yr) from Drinking Groundvater Contaminated by Radionuclides
Released by Fault Movement in GRANITE
3350 Years After Repository Sealing
Repository Water Affected
DISTANCE (aeter»)
20.00
1.83K+02
SN-126
54. 9Z
1.22E+02
SH-126
89.51
5.57S+04
AM-241
41.5%
1.09F+Q5
AH-241
39.81
7.41E+04
AM-241
36.4X
4.5QE+04
AH-243
27.7Z
9.48E+03
AM-243
31.91
7.34E+03
A!i-243
35. 5Z
4.05E+03
AM-243
34.81
1.77E+03
PU-239
39. 9Z
50.00
1.90E+02
SH-126
53. OX
1. 75E+02
SH-126
62.21
5.57E+04
AM-241
41.52
1.09E+05
AM-241
39.81
7.42E+04
AM-241
36.4Z
4.50E+04
AM-243
27. n
3.18E*04
AH-Z43
31.9Z
2.43E+04
AM-243
35.51
7.48E+03
AM-243
34. 8Z
3,Z7E*03
FU-239
39. 9S
100.00
1.90E+02
SN-126
53. OZ
1.75E+02
SH-126
52..2Z
5.58B+04
AM-241
41. 5Z
1.09E+05
AM-241
39. 8X
7.42E+04
AM-241
36.4Z
4.50E+04
AH-243
27. 7Z
3.181*04
AH-243
31. 9Z,
2.43E+04
AM-243
35. 5Z
1.21E+04
AM-243
34.81
5.30S+03
PU-239
39.9Z
200.00
1.90E+02
SN-126
53. OX
1.75E+02
SH-126
62.2Z
5.58S+04
AM-241
41.4Z
1.09E+05
AM-241
39. BZ
7.42E+04
AM-241
36.4Z
4.51S+04
AM-243
27. 7Z
3.18E+04
AM-243
31.9X
2.43E+04
AM-243
35. 5X
1.38E+04
AM-243
34, 8X
9.43B+03
P3-239
39. 9Z
500.00
1.901+02
SN-126
53. OZ
1.75E+02
SM-126
62, 2 1
5.58B+04
AM-241
41.4Z
1.09E+05
AM-241
39. BZ
7.42E+04
AM-241
36.4Z
4.51E+04
AM-243
27. 7Z
3.18E*04
AH-243
31.9%
2.43E+04
AM-243
35. 5Z
1.88E+04
AH-243
34. 8Z
1.30E+04
PU-239
39. 9X
750.00
1.90E+02
SN-126
53. OZ
1.75E+02
SH-126
62.21
5.58E+04
AH-241
41.4Z
1.09E+05
AM-241
39. BZ
7.42E+04
AM-241
36.4Z
4.51S+04
AM-243
27. 7Z
3.18S+04
AH-243
31. 9Z
2.43E+04
AM-243
35. 5Z
1.88E+04
AH-243
34. 8Z
1.301*04
PU-239
39. 9Z
1000.00
1.90E+02
SN-126
53. OZ
1.75B+02
88-126
62.21
5.S8E+04
AM-241
41.4Z
1.091+05
AM-241
39.81
7.42E+04
AM-241
36.4Z
4.51S+04
AH-243
27. ?Z
3.18E+04
AH-143
31. 9Z
2.43E+04
AH-Z43
35. 5%
1.88E+04
AM-243
34.81
1.30E+04
PO-239
39. 9Z
1500.00
1.90E+02
SN-126
53.0Z
1.75E+02
SH-126
62.2Z
5.58E+04
AH-241
41.4Z
1.09E+05
AM-241
39. BZ
7.42E+04
AM-241
36.4Z
4.51B+04
AM-243
21, 7Z
3.18S+04
AH-243
31. 9%
2.43S+04
AM-243
35. 5Z
1.88E+04
AM-243
34. 8Z
1.30E*04
PU-239
39. 9Z
2000.00
1.90E+02
SN-126
53.0Z
1.75E+02
SH-126
62.2Z
5.58B+04
AH-241
41.4Z
1.09E+05
AH-241
39.8Z
7.42E+04
AH-24J.
36. 4Z
4.51E+04
AH-243
27. 7Z
3.18E+04
AH-243
31. 9Z
2.43E+04
AM-Z43
35. 5Z
1.88E+04
AM-243
34. 8Z
1.30S+04
PB-239
39. 9Z
4000.00
1.90E+02
SH-126
53. OZ
1.75E+02
SH-124
62. ZZ
5.58E+04
AH-241
41.4Z
1.09E+05
AM-241
39.8Z
7.42E+04
AH-241
36.4Z
4.51E+04
AM-243
27. 7Z
3.18B+04
AM-243
31.9Z
2.43E+04
AM-243
35. 5Z
1.88E+04
AM-243
34. BZ
1.30E+04
PO-239
39. 9Z
-------
TIME (yr)
l.OOE+Ol
2.00E+01
5.00E+01
l.OOE+02
2.00B+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
Table 5.29
Dose Equivalent Rates (rem/yr) from Drinking Groundwater Contaninated by Radlonuelides
Released by Fault Movement in GRANITE
7500 Years After Repository Sealing
Repository Water Affected
DISTANCE (deters)
20.09
3.55E+02
SR-126
56.01
2.38E+02
SH-126
90.02
4.92E+04
AM-Z43
35,31
9.77E+04
AM-243
35.31
6.85E+04
AM-243
35.3%
4.401*04
AM-243
35.12
3.9SE+03
AM-243
34.7%
3.34E+03
PU-239
34.81
2.04E+03
PU-239
38.81
9.15E+02
PU-239
45.2Z
50.00
3.67E+02
SH-126
54.02
3.39E+02
SH-126
63.21
4.921+04
AM-243
35.31
9.77E+Q4
AM-243
35.31
6.86E+04
AH-243
35.21
4.40E+04
AH-243
35.11
3.221+04
AM-243
34. 7Z
2.40E+04
PU-239
34. 8%
3.76B+03
PU-239
38.851
1. 691+03
PU-239
45.21
100,00
3.67E+02
SH-126
54.0%
3.39E+02
SH-126
63.22
4.93E+04
AM-243
35.31
9.77E+04
AM-243
35.31
6.86E+04
AH-243
35.21
4.40E+04
AM-243
35. 1Z
3.22E+04
AM-243
34. 7*
2.40E+04
PU-239
34.81
6.08E+03
PU-239
38. 8Z
2.74E+03
PU-239
45.22
200.00
3,671+02
SH-126
54.0%
3.39E+02
SH-126
63. 2*
4.93E+04
AH-243
35. 2%
9.77E+04
AM-243
35. 3t
6.86E+04
AM-243
35. 21
4.40E+04
AM-243
35. OZ
3 . 221+04
AM-243
34. 7Z
2.40E+Q4
PU-239
34.82
1.59E+04
PU-239
38.82
4.87B+03
PU-239
45.2%
500,00
3.671+02
SH-126
54.0Z
3.39E+02
SH-126
63. 2Z
4.93E+04
AH-243
35.2*
9.7BE+04
AM-243
35.3%
6.86E+04
AM-243
35.21,
4.40E+04
AH-243
35.01
3.22E+04
AM-243
34. n
2..41E+04
PU-239
34.8%
1.59E+04
PU-239
38.82
l.Oli+04
PU-239
45.3X
750.00
3.67E+02
SH-126
54.01
3.39E+02
SH-126
63. 2Z
4.93S+04
AH-243
35.2Z
9.78S+04
AM-243
35,31
6.86E+04
AM-243
35. 2*
4.40E+04
AH-243
35. OZ
3.22E+04
AM-243
34. 7Z
2.41E+04
PU-239
34.82
1.59E+04
PU-239
38.82
1.01E+04
PU-239
45.22
1000.00
3.67E+02
SH-126
54.0%
3.39E+02
SH-126
63.22
4.931+04
AH-243
35.22
9.788+04
AM-243
35.32
6.86E+04
AM-243
35.22
4.40E+04
AM-243
35. OZ
3.22E+04
AM-243
34.72
2.41E+04
PU-239
34.82
1.59E+04
PU-239 •
38.82
1.01E+04
PU-239
45.22
1500.00
3.67E+02
SS-126
54.02
3.39E+02
SH-126
63.2X
4.93E+04
AK-243
35.2%
9.78E+04
AM-243
35.32
6.86E+04
AH-243
35.22
4.40E+04
AH-243
35.02
3.22E+04
AM-243
34. 7Z
2.41E+04
PU-239
34. 8Z
1.59E+04
PU-239
38.72
1.01E+04
PU-239
45.22
2000.00
3.67E+02
SH-126
54.02
3.39E+02
BH-126
63. 2Z
4.93E+04
AH-243
35.2%
9.78E+04
AM-243
35.32
6.86E+04
AM-243
35.21
4.40E+04
AM-243
35.02
3.22S+04
AM-243
34. 7%
2.41E+04
PU-239
34.82
1.59E+04
PU-239
38.7%
1.01E+04
PU-239
45.22
4000.00
3.67E+02
SH-126
54.02
3.39E+02
SH-126
63.2%
4.93E+04
AH-243
35.2%
9.78E+04
AM-243
35.3%
6.86E+04
AM-243
35.22
4.40E+04
AH-243
35.0%
3.23S+04
AM-243
34.7%
2.41E+04
PU-239
34.8%
U59E+04
PU-239
38.72
1.01E+04
PU-239
45.22
-------
is removed by decay, soil penetration, and secondary resuspension.
Dose rates from later releases are lower than those from earlier
releases because of more radionuclide decay before the event.
We can estimate the contaminated areas by noticing that the
concentration equations are independent of direction. To ascertain the
area contaminated above a given value, the code interpolates to find
the distance at which that dose is incurred, and finds the area of a
circle lith the distance as the radius. This gives a picture of the
land surface contaminated above a selected level.
In the 1000-year event, Table 5.2 shows Am-241 as the dominant
radionuclide for tha first 500 years. The longer-lived Pu-239 and -240
dominate the rest of the table. Doses are moderate, the highest being
11 rem/yr at 20 meters and 10 years, and decrease rapidly with distance
and slowly with time. The 200-year event (Table 5.30) is dominated by
Am-241 for 500 years, then ,by Pu-239 and -240. The 3350-year and
7500-year events (Tables 5.31 and 5.32) are dominated by Pu-239 and
Pu-240. As the total time increases the dose rates and areas
contaminated decrease due primarily to radiological decay.
Table 5.33 shows the areas contaminated above specified dose
levels. For early drilling, at 200 and 1000 years after repository
sealing, more than 10 ha are contaminated enough to give dose rates
above 0.5 rem/yr for fairly long periods of time. Smaller areas are
contaminated enough to give dose rates of 5 rem/yr. For later
drilling, at 3350 and 7500 years after sealing, less than three ha are
contaminated enough to give dose rates above 0.5 rem/yr and none are
contaminated enough to give 5 rem/yr.
5.3.2 Brine pocket
Tables 5.34 through 5.37 give the annual dose rates resulting from
releases of waste to the land surface by drilling into a brine pocket.
The annual dose rates for this release scenario are much smaller than
those from the direct hit case discussed in the previous section. The
largest dose rate calculated is only 0.02 rem/yr, 90X from Am-241.
100
-------
Table 5.30
Done Equivalent Rates (rem/yr) from Breathing Air Contaminated by Radionuclides
Released by Borehole Drilling
ZOO Years After Repository Sealing
Drill Hits Waste
DISTAHCE (m€t«r«)
TIME (yr)
l.OOE+Oi
2.0QE+01
5.00E-W1
l.OOE+02
2.QQE+02
5.00B+02
l.OQE+03
2.0QB403
5.00E+03
1.00B404
20,00
2,881+01
AH-241
70.71
2.81E+01
AM-241
71,0%
2.62K+01
AM-241
71. 1%
2.35E+01
AH-241
72.21
1.93E+01
AM-241
71.82
1, 17E+01
AM-241
64. 72
S.82B+00
AM-241
47. 41
2.09E+00
TO-240
44.92
3. 092-01
PU-240
49.12
1.80E-02
PU-239
57. 61
50.00
7.61B+00
AM-241
70.72
7.42E+00
AH-241
71.02
6.92E+00
AM-241
71,72
6.21E+QO
AM-241
72. ZI
S.11S+00
AM-241
71.81
3.09E+00
AH-241
64.72
1.S4E+00
AM-241
47.4Z
5.511-01
PU-240
44.91
8.16E-02
PU-240
49. U
4.76E-03
PU-239
57.6X
100.00
2.768+00
AH-241
70. 7Z
2.69E+00
AH-241
71.02
2.51E+00
AH-241
71. 7X
2.25K+00
AH-241
72.2Z
l.SSEfOO
AH-241
71.8Z
1.12E+00
AH-241
64. 7Z
5.571-01
AM-241
47.4Z
2.00E-01
PU-240
44. 9%
2.96B-02
PU-240
49. 1Z
1.72B-03
PU-239
57. 6Z
200.00
9.87E-01
AH-241
70. 7Z
9.63B-01
AK-241
71.0Z
8.981-01
AH-241
71.7Z
8.06E-01
AM-241
72.2Z
6.63E-01
AM-241
71. 8Z
4.01B-01
AH-241
64. 7Z
1.99E-01
AM-241
47. 4Z
7.15E-02
PU-240
44. 92
1.06B-02
PU-240
49. 1Z
6.17E-04
PO-239
57.62
500.00
2.471-01
AM-241
70.72
2.41E-01
AH-241
71. OZ
2.25E-01
AH-241
71.7Z
2.02E-01
AM-241
72.2Z
1.66E-01
AM-241
71.82
l.OOE-01
AH-241
64.72
4.991-02
AM-241
47.42
I. 79E-02
PU-240
44, 9Z
2.65B-03
PU-240
49.12
1.54E-04
PU-239
57.62
750.00
1.328-01
AH-241
70.72
1.29E-01
AH-241
71.02
1.20E-01
AM-241
71.7Z
1.08E-01
AH-241
72,22
8.84K-02
AM-241
71,8%
5.35E-02
AM-241
64.7Z
2.66E-02
AM-241
47.42
9.54E-03
PO-240
44.92
1.41E-03
PU-240
49.1%
8.23E-05
PU-239
57.61
1000.00
8.37E-02
AM-241
70.72
8.17S-02
AH-241
71.02
7.82E-02
AM-241
71. 7Z
S.84E-02
AM-241
72.22
5.62E-02
AH-241
71.8Z
3.40B-02
AH-241
64.72
1.69E-02
AM-241
47.4Z
6.07E-03
PU-240
44.92
8.98E-04
PU-240
49.12
5.23E-05
PU-239
57.62
1500.00
4.36B-02
AM-241
70.72
4.26E-02
AM-241
71.0Z
3.97E-02
AM-241
71.72
3.56E-02
AH-241
72.22
2.93B-02
AM-241
71.82
1.77E-02
AH-241
64.72
8.82E-03
AH-241
47.42
3.16E-03
PU-240
44.92
4.68E-04
PU-240
49.12
2.73E-05
PU-239
57.6%
2000.00
2.72E-02
AH-241
70.72
2.65E-02
AH-241
71.02
2.47E-02
AH-241
71.72
2. 221-02
AH-241
72.22
1.83E-02
AH-241
71.82
l.HE-02
AM-241
64. 7Z
5.50E-03
AH-241
47.42
1.97E-03
PU-240
44. 9Z
2.92E-04
PU-240
49.1%
1.70E-05
PU-239
57.62
4000.00
8.27E-03
AM-241
70.72
8.08E-03
AH-241
71.0Z
7.53E-03
AM-241
71.72
6.76E-03
AM-241
72.22
5.56E-03
AH-241
71.8%
3.36E-03
AM-241
64.72
1.67E-03
AH-241
47.42
6.00E-04
PU-240
44.92
8.87E-05
PU-240
49.12
5.17E-06
BU-239
57.62
-------
o
PO
Table 5.31
Dose Equivalent Rates (reio/yr) Iron Breathing Air Contaminated by Radionuclideo
Released by Borehole Drilling
3350 Tears After Repository Sealing
Drill Hits Waste
DISTANCE (otters)
TIME (yr)
1.00E+Q1
2.00E+Q1
S.OOB+Ol
1.001+02
2.00E+02
5.00K+02
I. OOE+03
2.00E+03
5.00E+03
l.OOE+04
20,00
4.5US+00
PU-240
50,4%
4.48E+00
PU-240
50.41
4.39E+00
PU-240
50.51
4.26E+OQ
FU-240
50.5%
4.0QE+00
PU-240
50.6J
3.33E+00
PU-240
50.61
2.48E+00
PU-240
50,21
1.39B+00
PU-240
48.8%
2.52E-01
PO-239
54,3%
1.50E-02
PU-239
63. 01
50.00
1.19E+00
PU-240
50.4%,
1. 18E+00
HJ-240
50.4%
1.161+00
PU-240
50.5%
1. 13E+00
IU-240
50, 5Z
1.06E+00
HJ-240
50.6%
8.8JE-01
HJ-240
50,6%
6.55E-01
PU-240
50. 2X
3.67B-01
fU-240
48.81
6.65E-02
PU-239
54. 3%
3.97E-03
PU-239
63.0%
100.00
4.32E-01
PU-240
50.4Z
4.29E-01
PU-240
50. 4Z
4.21E-01
PU-240
50.5Z
4.08B-01
PU-240
50.5Z
3.83E-01
PU-240
50.61
3.19E-01
PU-240
50.6J
2.37E-01
PU-240
50. 2Z
1.33E-01
PU-240
48.8:
2.41E-02
W-239
54. 3Z
1.44E-03
PU-239
63.0Z
200,00
-1.55E-01
PU-240
50.41
1.54E-01
FU-240
50.4Z
1.511-01
TO-240
50. 5Z
1.461-01
PU-240
50. 5Z
1.37E-01
PU-240
50.6*
1, 14E-01
PU-240
50.6%
8.50E-02
PU-240
50.2%
4.76E-02
PU-240
48.8%
8.62E-03
PU-239
54. 3 Z
5.15E-04
PU-239
63. 0%
500,00
3.87E-02
PU-240
50.4X
3..84E-02
PU-240
50 .41"
3.778-02
PU-240
50. 5Z
3.658-02
PU-240
50.5%
3.43E-02
PU-240
50.6%
2.86B-02
PU-240
50.6%
2.13E-02
PU-240
50.2%
1. 191-02
PU-240
48,8%
2.16E-03
PU-239
54.3%
1.29E-04
PU-239
63.0%
750.00
2.06E-02
PU-240
50.4%
2.051-02
PU-240
50.4Z
Z.011-02
PU-240
50.5%
1.95E-02
PU-240
50.51
1.83E-02
PU-240
50.6%
1.53E-02
PU-240
50.6%
1.131-02
PU-240
50.2%
6.361-03
PU-240
48.8%
1.15E-03
PU-239
54.3%
6.87E-05
PU-239
63.0%
1000.00
1.31E-02
PU-240
50.4%
1.30S-02
PU-240
50.4%
1.28E-02
PU-240
50. 5%
1.24E-02
PU-240
50.51
1.16E-02
PU-240
50. 6 J
9.701-03
PU-240
50.61
7.21E-03
PU-240
50. 2Z
4.04E-03
PU-240
48.8%
7.31E-04
PU-239
54.3%
4.37E-05
PU-239
S3.0Z
1500.00
6.B4E-03
PU-240
S0.4Z
6.79E-03
PU-240
50. 4Z
6.66E-03
FU-240
50.5%
6.46E-03
PU-240
50, 5Z
6.07E-03
PU-240
50.6%
5.06E-03
PU-240
50.6%
3.76E-03
PU-240
50.2%
2.11B-03
PU-240
48.8%
3.81E-04
PU-239
54.3%
2.28E-05
PU-239
63.0%
2000.00
4.26E-03
PU-240
50 .4%
4.23E-03
PU-240
50.4%
4.15F 03
FU-240
50.5%
4.02B-03
PU-240
50. 5X
3.78E-03
PU-240
50.6%
3.15E-03
PU-240
50.6%
2.34E-03
PU-240
50.2%
1.31E-03
PU-240
48.8%
2.38E-04
PU-239
54.3%
1.42E-05
PU-239
63.0%
4000.00
1.30E-03
PU-Z40
50.4%
1.29S-03
PU-240
50.4%
1.26B-03
PU-240
50.5Z
1.22E-03
PU-240
50.5%
1.15E-03
PU-240
50.6%
9.59E-04
PU-240
50.61
7.13E-04
PU-240
50.2%
4.00E-04
PO-240
48.81
7.23E-05
FJ-239
54.3%
4.32E-06
PU-239
63. OZ
-------
Table 5.32
TIMS (yr)
l.OOE+01
2.00E+01
5.00E+01
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
Dose Equivalent: Rates (rem/yr) from Breathing Air Contaminated by Radionuclidea
Released by Borehole Drilling
7500 Years After Repository Sealing
Drill Hits Waste
DISTANCE (meter»)
20.00
3.3CE+00
HJ-239
52.71
3.28B+00
PU-239
52.8!
3.22E+OQ
PU-239
52. n
3.13E+QO
PU-239
53.0%
2.96E+00
PU-239
53.2%
2.49B+00
PU-239
53.71
1.88E+00
PU-239
54. 6%
1.071+00
TO-239
56.4%
1.97E-01
PU-239
61.61
1.201-02
PU-239
69. 7%
50.00
8.72E-01
PU-239
52. n
8.67E-01
PU-239
52.8%
8.51E-01
PU-239
52.91
8.27E-01
PU-239
53.0%
7.82E-01
PU-239
53.2%
6.59E-01
PU-239
53.7Z
4.96E-01
PU-239
54.61
2.82E-01
PU-239
56,4%
5.20E-')2
PU-239
61.61
3.18S-03
PU-239
69. 7S
100.00
3.16E-01
PU-239
52. n
3.141-01
PU-239
52. 8%
3.08B-01
PU-239
52.91
3.00E-01
PU-239
53.0%
2.83E-01
PU-239
53.21
2.39E-01
PU-239
$3.71
1.80E-01
PU-239
54.6%
1.021-01
PU-239
56.41
1.88E-OZ
PU-239
61.6%
1. 1SB-03
PU-239
69.7%
200.00
1.13E-01
PU-239
52.71
1.12E-01
PU-239
52.8%
1.10E-01
PU-239
52.9%
1.07E-01
PU-239
53.0%
1.01S-01
PU-239
53.2%
8.55E-02
PU-239
53,7%
6.44E-02
PU-239
54.6%
3.668-02
PU-239
56.4%
6.74E-03
PU-239
61.6%
4.13E-04
PU-239
69.7%
500.00
2.83E-02
PU-239
52.7%
2.81E-OZ
PU-239
52.8%
2.76E-02
PU-239
52.9%
2.68E-02
PU-239
53.0%
2.54E-02
PU-239
53.2%
2.14E-02
PU-239
53.7%
1.61E-02
PU-239
54.6%
9.14E-03
PU-239
56.4%
1.69E-03
PU-239
61,6%
1.03E-04
PU-239
69.7%
750.00
1.51B-02
PU-239
52.7%
1.50E-02
PU-239
52.8%
1.47K-02
PU-239
52,9%
1.43E-02
PU-239
53.0%
1.35S-02
PU-239
53.2%
1. 14B-02
PU-239
53.7%
8.59E-03
PU-239
54.6%
4.88E-03
PU-239
56 .'4%
9.00E-04
PU-239
61.6%
5.51S-05
PU-239
69.7%
1000.00
9.60E-03
Ptl-239
52.7%
9.54B-03
PU-239
52.8%
9.37E-03
PU-239
52.9%
9.101-03
PU-239
53,0%
8.60E-03
PU-239
53.2%
7.25E-03
FU-239
53.7%
5.46E-03
PU-239
54.6%
3.10B-03
PU-239
56.4%
5.72E-04
PU-239
61.6%
3.50E-05
PU-239
69.7%
1500.00
5.00E-03
PU-239
52.7%
4.97E-03
PU-239
52.8%
4.88E-03
PU-239
52.9%
4.75E-03
PU-239
53.0%
4.48E-03
PU-239
53.2%
3.78E-03
PU-239
53.7%
2.85E-03
PU-239
54.6%
1.62E-03
PU-239
56.4%
2.98E-04
PU-239
61.6%
1.83E-05
PU-239
69.7%
2000.00
3.121-03
PO-239
52.7%
3.10E-03
PU-239
52.8%
3.04E-03
PU-239
52.9%
2.96E-03
PU-239
53.0%
2.79E-03
PU-239
53.2%
2.36E-03
PU-239
53.7%
1. 77E-03
PU-239
54.6%
1.01E-03
PU-239
56.4%
1.86E-04
PU-239
61.6%
1. 14E-05
PU-239
69.7%
4000.00
9.49E-04
PU-239
52.7%
9.43E-04
PU-239
52.8%
9 . 26E-04
PU-239
52.9%
9.00E-04
PH-239
53.0%
8.50E-04
PU-239
53.2%
7.17E-04
PU-239
53.7%
5.408-04
PU-239
54.6%
3.07E-04
PU-239
56.4%
5.65E-05
PU-239
61.6%
3.46E-06
PU-239
69.7%
-------
Table 5.33
Area (ha*) of the Land Surface Contaminated
Above the Specified Dose Rate Levels Following
a Direct Drilling Hit on Waste
Dose Level (rem/yr)
0.5 5 50 500
Time After
Drill (yr)
10
20
50
100
200
500
1,000
2,000
5,000
10,000
200 years after
50
49
45
39
28
11
4.2
1.0
0
0
1.8
1.8
1.6
1.4
0.8
0.6
0.2
0
0
0
0
0
0
0
0
0
0
0
0
0
sealing
0
0
0
0
0
0
0
0
0
0
Dose Level (rem/yr)
0.5 5 50 500
0
0
0
0
0
0
0
0
0
0
1000 years aftc
11
10
10
10
8.3
4.8
2.5
0.8
0
0
0.6
0.6
0.5
0.5
0.4
0.2
0
0
0
0
0
0
0
0
0
0
0
0
0
0
3350 years after sealing
7500 years after sealing
10
20
50
100
200
500
1,000
2,000
5,000
10,000
2.6
2.5
2.5
2.4
2.2
1.7
1.1
0.5
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
1.7
1.6
1.6
1.5
1.4
1.2
0.8
0.4
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
*1 hectare (ha) = 10^ square meters
104
-------
fable 5.34
O
in
TIHE (yr)
l.OOE+01
2.00E+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
i.OGE+04
Dose Equivalent Rate* (res/yr) from Breathing Air Contaminated by Radionucltdei
Released bjr Borehole Drilling in BEDDED SALT
1000 tears After Repository Sealing
Drill Hits Repository Hater
DISTANCE (metero)
20.00
1.74E-02
AM-241
90,51
1.70E-02
AM-241
90.61
1.59E-Q2
AH-241
91.02
1.43E-02
AM-241
91. 31
1.17E-02
AH-241
91,41
6.58E-03
AM-241
88.9%
2.67E-03
AM-241
79.9%
5.78E-04
AM-243
51. OX
5.0 IE -05
AM-243
98.7%
2.52E-06
AM-243
100.0%
50.00
4.59E-03
AM-241
90.51
4.49E-03
AM-241
90.61
4.21E-03
AM-241
Sl.QZ
3.79E-03
AM-241
91.31
3.10E-03
AH-241
91.4Z
1. 74E-03
AH-241
88.9!
7.05E-04
AH-241
79. 9Z
1.53E-04
AM-243
51. OJ
1.32E-05
AM-243
98.71
6.65E-07
AM-243
100.0%
100.00
1.66E-03
AM-241
90.52
1.63E-03
AM-241
90.6%
1.531-03
AM-241
91.01
1.37S-03
AM-241
91.3%
1.12E-03
AH-241
91.41
6.30E-04
AM-241
88.01
2.55E-04
AM-241
79. 9Z
5.54E-05
AM-243
51. OZ
4.80E-06
AM-243
98. 7Z
2.41E-07
AH- 243
100. OZ
200.00
5.95E-04
AM-241
90, 5%
5.83E-04
AH-241
90.6%
5.46K-04
AM-241
91.0%
4.92E-04
AM-241
91. 3Z
4.02E-04
AM-241
91. 4Z
2.261-04
AM-241
88.91
9.14E-05
AM-241
79. 9Z
1.98E-05
AM-243
51. OZ
1.72E-06
AM-243
98. 7%
8.62E-08
AH-243
100. OZ
500.00
1.49E-04
AM-241
90.51
1.46E-04
AH-241
90.62
1.3 71-04
AH-241
91.02
1.23E-04
AM-241
91. 3%
l.OOE-04
AM-241
91. 4%
5.64E-05
AH-241
88. 9Z
2.29E-05
AM-241
79. 9Z
4.96E-06
AM-243
51. OZ
4.29E-07
AM-243
98.72
2.16E-08
AM-243
100. OZ
750.00
7.95E-05
AM-241
90.5%
7.78E-05
AM-241
90.62
7.29E-OS
AH-241
91.02
6.561-05
AM-241
91.3%
5.36E-05
AH-241
91. 4Z
3.01E-05
AM-241
88.91
1,221-05
AH-241
19.91
2.65E-06
AH-243
51. OZ
2.29E-07
AM-243
98. 7Z
1.15E-08
AH-243
100. OZ
1000.00
5.05E-05
AM-241
90.52
4.94E-05
AM-241
90.62
4.63E-05
AM-241
91.0%
4.17E-05
AM-241
91. 3Z
3.41E-05
AM-241
91.42
1.91E-05
AM-241
88.92
7.76E-06
AM-241
79.92
1.68E-06
AM-243
51,02
1.46E-07
AM-243
98. 7%
7.32E-09
AM-243
100.0%
1500.00
2.63E-05
AM-241
90.5%
2.58E-05
AH-241
90.62
2.42E-05
AH-241
91.02
2.18E-05
AM-241
91.32
1.78E-05
AM-241
91.42
9.97E-06
AM-241
88.91
4.04E-06
AM-241
79.92
8.77E-07
AM-243
51.01
7.59E-08
AM-243
98.7%
3.81E-09
AM-243
100.0%
2000.00
1.64E-05
AM-241
90.52
1.611-05
AM-241
90.62
1.50E-05
AM-241
91.02
1,361-05
AM-241
91.32
1.11E-05
AM-241
91.42
6.21E-06
AM-241
88.92
2.528-06
AM-241
79. 9Z
5.46E-07
AM-243
51.0%
4.73E-08
AM-243
98.72
2.38E-09
AM-243
100. OZ
4000.00
4.99E-06
AM-241
90.5%
4.89E-06
AM-241
90.62
4.58E-06
AH-241
91.0%
4.1ZE-06
AM-241
91.32
3.37E-06
AM-241
91.42
1.89E-06
AM-241
88.92
7.67E-Q7
AM-241
79. 9Z
1.66E-07
AH-243
51.0%
1.44E-08
AM-243
98.72
7.23E-10
AH-243
100.0%
-------
Table 5.35
O
01
TIME (yr)
i.OOE+Ql
2.00E+01
5.00E+01
l.QQE+02
2.00E-M)2
5.00E+02
l.OOE+03
2.00E*03
5.00E+03
l.OOB+04
Dose Equivalent Rates (rera/yr) from Breaching Air Contaminated by Radionuclidco
Released by Borehole Drilling In BEDDED SALT
200 Years After Repository Sealing
Drill Hits Repository Water
DISTANCE (meters)
20.00
5.71E-Q2
PU-238
70, 71
5.36E-02
PU-238
69.41
4.45E-02
PU-238
65.2%
3.32E-02
FU-238
57.71
1.99E-02
AM-241
53.7%
7.26E-03
AM-241
80.5%
2.6SE-03
AM-241
79.6X
5.78E-04
AM-243
51. OX
5.01E-05
AH-243
98,7%
2.52E-06
AM-243
100.0?
50.00
1.51E-02
PU-238
70.71
1.42E-02
PU-238
69.4%
1.17B-02
PU-238
65.21
8.77E-03
PU-238
57.71
5.27E-03
AM-241
53.7%
1.92E-03
AM-241
80.5%
7.081-04
AM-241
79. 6%
1.53E-04
AM-243
51.0Z
1.32B-05
AH-Z43
98.71
6.65E-07
A»-243
100.01
100.00
5.47E-03
HJ-238
70.7%
5.13E-03
PU-238
69.4%
4.26S-03
PU-238
65. 2X
3.18E-03
PU-238
57. 7%
1.91E-03
AM-241
53.7%
6.95E-04
AM-241
80.5%
2.56E-04
AM-241
79.6%
5.54E-05
AH-243
51.0%
4.80E-06
AH-243
98.71
2.41E-07
AH-243
100.0%
200.00
1.96E-03
PU-238
70.7%
1.84E-03
PU-238
69.3%
1.S2E-03
PU-238
65.2%
1. 14E-03
TO-238
57.7%
6.83E-04
AH-241
53.7%
2.49E-04
AM-241
80.5%
9.18E-05
AM-241
79.61
1.98E-05
AM-243
51.0%
1.721-06
AM-243
9S.7%
8.62E-08
AM-243
100.0%
500.00
4.90S-04
PU-238
70.7%
4.60E-04
PU-238
69.41
3.81Z-04
PU-238
65.21
2.84E-04
PO-238
57.7%
1.71E-04
AM-241
53.7%
6.23E-05
AM-241
80.5%
2.30E-05
AM-241
79.6%
4.96B-06
AM-243
51.0%
4.29E-07
AM-243
98.7%
2.16E-08
AM-243
100.0%
750.00
2.61E-04
FU-238
70.7%
2.45E-04
PU-238
69.41
2.03E-04
FU-238
65.2%
1.52B-04
PU-238
57.7%
9.12E-05
AM-241
53.71
3.32E-05
AM-241
80.5%
1.23E-05
AM-241
79.6%
2.65E-06
AH-243
51.0%
2.29E-07
AM-243
93.7%
1. 15E-08
AM-243
100.0%
1000.00
1.66E-04
PU-238
70.7%
1.56E-04
PU-238
69.3%
1.291-04
PU-238
65.2%
9.65S-05
PU-238
57.7%
5.80E-05
AM-241
53.7%
2.11E-05
AM-241
80.5%
7. 791-06
AM-241
79.6%
1.68E-06
AM-243
51.0%
1.46E-07
AM-243
98.71
7.32E-09
AM-243
100.0%
1500.00
8.66E-05
PU-238
70.7%
8.13E-05
PD-238
69.3%
6.74B-05
PD-238
65.2%
5.03E-05
PU-238
57.7%
3.02B-05
AM-241
53.71
1.10E-05
AM-241
80.5%
4.06E-06
AM-241
79.6%
8.77E-07
AM-243
51.0%
7.59E-08
AH-243
98.71
3.81E-09
AM-243
100.0%
2000.00
5.40S-05
PU-238
70.7%
5.06E-05
TU-238
69.4%
4.201-05
P0-238
65.2%
3.131-05
PU-138
57.7%
1.88E-05
AM-241
53.7%
6.86E-06
AH-241
60,5%
2.53E-06
AM-241
79.6%
5.46B-07
AH-243
51.0%
4.73E-08
AM-243
98.71
2.38E-09
AM-243
100.0%
4000.00
1.64E-05
PU-238
70.7%
1.54E-05
PU-238
69.4%
1.28E-05
PU-238
65.21
9.54E-06
PU-238
57.7%
5.73E-06
AM-241
53.7%
2.09E-06
AM-241
80.5X
7.70E-07
AM-241
79.6%
1.661-07
AM-243
51.0%
1.44E-08
AM-243
98.7%
7.23E-10
AM-243
100.0%
-------
o
Table 5.36
Dose Equivalent Rates (ren/yr) from Breathing Air Contaminated by Radionuclides
ReleiMd by Borehole Drilling in BEDDED SALT
3350 Yean After Repository Sealing
Drill Hit* Repository Water
DISTANCE (metura)
TIME Cyr)
l.OOE-HJl
2.00E+Q1
5.00E+01
l.OOE+02
2.00E+02
5.00B+02
l.OOE+03
2.00E+03
5.00E+03
l.OQE+454
20.00
1.67E-02
AM-241
94, 2Z
1.64E-02
AH-241
94. 1Z
1.54S-02
AM-241
93.91
1.40E-02
AM-241
93.5*
1. 168-02
AM-241
92. 6Z
6.S7E-03
AM-241
89.0X
2.67E-03
AM-241
79. 9J
5.78B-04
AM-243
51.0Z
5.01E-0.r
AM-243
98. 7Z
2.52E-06
AM-243
100.0Z
50.00
4.41E-03
AM-241
94.21
4.32E-03
AM-241
94. 1Z
4.08E-03
AM-241
93, 9Z
3.71E-03
AH-241
93, SZ
3.06E-03
AH-241
92. 6Z
1.74E-03
AH-241
89.0X
7.05S-04
AH-241
79. 9*
1.53S-04
AM-243
51. OZ
1.32E-05
AM-243
98. 7Z
6.65E-07
AM-243
100, OZ
100.00
1.60E-03
AM-241
94. 2X
1.57E-03
AM-241
94. 1Z
1.48B-03
AM-241
93. 9*
1.34B-03
AM-241
93. SZ
1.11E-03
AM-241
92. 6X
6.29E-04
AM-241
89.01
2.55E-04
AM-241
79.9Z
5.54E-05
AM-243
51. OZ
4.80E-06
AM-243
98, 7Z
2.41E-07
AH-243
100. OZ
200.00
5.72E-04
AH-241
94.2Z
5.61E-04
AH-241
94, 1Z
5.29E-04
AM-241
93. 9Z
4,818-04
AM-241
93. SZ
3.97E-04
AM-241
92.6X
2.25E-04
AM-241
89.0Z
9.141-05
AM-241
79.9X
1,981-05
AM-243
51.0Z
1.72E-OS
AM-243
98. 7Z
8.62E-08
AM-243
100. OZ
500.00
1.43E-04
AM-241
94.21
1.40E-04
AM-241
94. 1Z
1.32E-04
AM-241
93. 9Z
1.20E-04
Att-241
93. 5Z
9.92E-05
AM-241
92.61
5,631-05
AH-241
89.01
2.29B-05
AM-241
79. 9Z
4.96E-06
AM-243
51.0X
4.29E-07
AH-243
98. 71
2.16E-08
AM-243
100 .02
750.00
7.63E-05
AM-241
94.2Z
7.49E-05
AM-241
94. IX
7.06E-05
AM-241
93.9Z
6.41B-05
AM-241
93.5X
3.2SE-05
AM-241
92. 6Z
3.00E-05
AM-241
89.0Z
1.221-05
AM-241
79. 9Z
2.65E-06
AM-243
51. OZ
2.29S-07
AM-243
93.71
1.15E-08
AH-243
100. OZ
1000.00
4.85E-05
AM-241
94. 2Z
4.76E-05
AM-241
94. IX
4.49E-05
AH-241
93. 9Z
4.08E-05
AH-241
93. 5Z
3.37E-05
AM-241
92.6Z
1.9W-05
AM-241
89. OZ
7.761-06
AM-241
79.9Z
1.68E-06
AH-243
51.0Z
1.46E-0?
AM-243
SB. 71
7.32E-09
AM-243
100. OZ
1500.00
2.53E-05
AH-241
94. 2X
2.481-05
AH-241
94. IX
2.34E-05
AH-241
93. 9S
2.13S-05
AH-241
93. 51
1.75E-05
AM-241
92.6Z
9.96E-06
AH-241
89.0Z
4.048-06
AH-241
79.9Z
8.77E-07
AM-243
51.0Z
7.59E-08
AM-243
98. 7Z
3.81E-09
AM-243
100. OZ
2000.00
1.58E-05
AH-241
94.21
1.55E-05
AM-241
94. IX
1.46E-05
AM-241
93. 9Z
1.32E-05
AM-241
93. 5Z
1.0JE-05
AM-241
92. 6X
6.20E-06
AM-241
89.0Z
2.52E-06
AM-241
79.9Z
5.46E-07
AM-243
51.0Z
4. 73E-OB
AM-243
9B.7X
2.38E-09
AM-243
100.0Z
4000.00
4.80E-06
AM-241
94. 2 Z
4.70E-06
AM-241
94. IX
4.44E-06
AM-241
93.9Z
4.03E-06
AM-241
93. 5X
3. 331-06
AH-241
92, 6X
1.89B-06
AM-241
89.0Z
7.67E-07
AM-241
79. 9Z
1.66E-07
AH-243
51.0Z
1.44E-08
AM-243
98. 7Z
7.23E-10
AM-243
100. OZ
-------
o
oo
TIME (yr)
l.OOE+01
2.00E+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
Table 5.37
Dose Equivalent Rateo (rea/yr) from Breathing Air Contaminated by Radionuclides
Released by Borehole Drilling in BEDDED SALT
7500 Yeara After Repository Sealing
Drill Hits Repoaitory Water
DISTANCE (netera)
20.00
1.20E-03
AH-243
80.61
1.19E-03
AM-243
80.82
1.16E-03
AM-243
81.51
1.11E-03
AM-243
82.51
1.02E-03
AH-243
84. SZ
8.07E-04
AH-243
89. 3Z
5.67E-04
AM-243
94. 4Z
2.99E-04
AM-243
98. 6Z
4.94E-05
AM-243
100. OZ
2.52E-06
AM-243
100. OZ
50.00
3.16E-04 .
AM-243
80.61
3.14E-04
AM-243
80. 8Z
3.06E-04
AH-243
81. 5X
2.93E-04
AM-243
82. 5Z
2.70E-04
AM-243
84. 5Z
2.13E-04
AM-243
89. 3Z
1.50E-04
AM-243
94.4Z
7.91E-05
AM-243
98. 6Z
1.31E-05
AM-^43
100. OZ
6.65E-07
AM-243
100. OZ
100.00
1.15E-04
AM-243
80. 6Z
1. 14E-04
AH-243
80. 8Z
1.11E-04
AH-243
81.5Z
1.06E-04
AH-243
82. 5Z
9.77E-05
AH-243
84. 5Z
7.73E-05
AM-243
89. 3Z
5.43E-05
AM-243
94. 4Z
2.87E-05
AM-243
98. 6*
4.73E-06
AM-243
100. OZ
2.41E-07
AH-243
100. OZ
200.00
4.10E-05
AM-243
80. 6Z
4.07E-05
AH-243
80. 8t
3.97E-05
AM-243
81. 5Z
3.80E-05
AH-243
82. 5Z
3.50E-05
AM-243
84. 5Z
2.77E-05
AM-243
89. 3Z
1.94E-05
AM-243
94.4%
1.03E-05
AM-243
98. 6Z
1.69E-05
AM-243
100. OZ
8.62E-08
AM-243
100. OZ
500.00
1.03E-05
AM-243
80. 6Z
1.02E-05
AM-243
80.81
9.92E-06
AM-243
81.5Z
9.50E-06
AM-243
82.5%
8.75E-06
AH--243
84. 5X
6.92E-06
AM-243
89. 3Z
4.86E-06
AM-243
94. 4Z
2.57E-06
AM-243
98. 6Z
4.24E-07
AM-243
100. OZ
2.16E-08
AM-243
100. OZ
750.00
5.48E-06
AM-243
80. 6Z
5.43E-06
AH-243
80.8Z
5.29E-06
AH-243
81.5Z
5.07E-06
AH-243
82. 5*
4.67E-06
AM-243
84. 5Z
3.69E-06
AM-243
89. 3*
2.59E-06
AK-243
94. 4Z
1.37E-06
AM-243
98. 61
2.26E-07
AH-243
100. OZ
1. 15E-08
AH-243
100. OZ
1000.00
3.48E-06
AH-243
80. 6Z
3.45E-06
AH-243
80. 8Z
3.36E-06
AM-243
81. 5Z
3.22E-06
AH-243
82. 5Z
2.97E-06
AM-243
84. 5Z
2.35E-06
AM-243
89. 31
1.65E-06
AM-243
94. 4Z
8.70E-07
AM-243
98. 6Z
1.44E-07
AM-243
100. OZ
7.32E-09
AH-243
100. OZ
1500.00
1.82E-05
AM-243
80.6:
1.80E-06
AM-243
80.8X
1.75E-06
AM-243
81. 5Z
1.68E-06
AM-243
82. 5J
1.55E-06
AM-243
84.5;
1.22E-06
AM-243
89. 3Z
8.59E-07
AM-243
94. 4Z
4.54E-07
AM-243
98. 6Z
7.49E-08
AM-243
100. OZ
3.81E-09
AM-243
100. OZ
2000.00
1.13E-06
AM-243
80.61
1. 12E-06
AM-243
80. 8Z
1.09E-06
AH-243
81.5Z
1.05E-06
AM-243
82. 5Z
9.64E-07
AM-243
84. 5Z
7.62E-07
AH-243
89. 3%
5.35E-07
AM-243
94.4Z
2.83E-07
AH-243
98. 6Z
4.67E-08
AH-243
100. OZ
2v38E-09
AH-243
100. OZ
4000.00
3.44E-07
AH-243
80. 6Z
3.41E-07
AH-243
80. 8T.
3.33E-07
AM-243
81.5Z
3.19E-07
AH-243
82. 5Z
2.93E-07
AH-243
84. 5Z
2.32E-07
AM-243
89. 3Z
1.63E-07
AM-243
94. 4Z
8.60E-08
AM-243
98. 6Z
1.42E-08
AM-243
100. OZ
7.23E-10
AM-243
100. OZ
-------
There is no contaminated area table presented since there were no areas
contaminated over 0.5 rem/yr in any case. Amerieium isotopes are
dominant except for some Pu-238 at early times. 'The low solubility of
3
the plutonium isotopes in the small brine pocket (0.06 m ) is
responsible for their lack of importance at all times. Where Pu-239
and Pu-240 were dominant in the direct hit case, they have been
replaced by Am-241 and Am-243 which have much larger solubility
limits. The nuelides in a brine pocket are dissolved and, therefore,
we use a different set of inhalation.DECF's than for the land surface
case where they were in an insoluble form.
5.3.3 Granite tank
Tables 5.38 through 5.40 give the annual dose rates resulting from
a release of water from a granite repository to the land surface by
drilling. The repository's void volume of 2 x 10 m has been
charged with water from the upper aquifer before canister failure.
Then, when the canisters fail, the nuclides from the failed canisters
leach or dissolve into the repository water. The inventories of the
nuclides in the repository water increase until radioactive decay
becomes more important than additional leaching. This overall effort
increases the potential dose rates until an event time of 1200 years,
when the potential dose rates begin to drop due to decay. For drilling
at 1000 years, Am-241 is the dominant nuclide for about 2000 years
after the event, but the highest dose rate is only 0.72 rem/yr. After
5000 years, the Am-241 has decayed to lower levels, and Ain-243 is the
dominant nuclide through 10,000 years. Dose rates are presented for
three event times: 1000, 3350, and 7500 years. There is no dose for
an event at 200 years because the canisters do not fail until 500 years
after sealing.
Here again no contaminated area table is presented since for
drilling at 1000 years only a very small area, about 0.2 ha, would be
contaminated enough to give a dose rate of more than 0.5 rem/yr. No
areas would be contaminated enough to give 0.5 rem/yr or higher from
drilling at 3350 or 7500 years.
109
-------
fable 5.38
Dote Equivalent Races (ren/yr) fro* Breathing Air Contaainated by Kadiomiclides
Released by Borehole Drilling in GRANITE
1000 Year* After Repository Sealing
Drill Kite Repository Water
DISTANCE (neter.)
TUB
-------
Table 5.39
Dose Equivalent Rates (rem/yr) from Breathing Air Contaminated by Radionuelidet
Released by Borehole Drilling in GRANITE
3350 Yeare After Repository Sealing
Drill Hit* Repository Hater
DISTANCE (meters)
TIME (yr)
l.OQE-KU
2.00E+01
5.00E+01
1.00E+Q2
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.QOE+Q3
l.OOE+04
20. DO
l,53E-Oi
AM-241
66.91
1.51E-01
AM-241
66.61
1.44E-01
AM-241
65.62
1.34E-01
AM-241
64.02
1.15E-01
AM-241
60.71
7.61E-02
AM-241
50.22
4.211-02
AM-243
66.8X
1.74E-02
AM-243
89.2?
2.60E-03
AM-243
99.62
1.32E-04
AM-243
99. 82
50.00
4,061-02
AH-241
66,91
3.99E-02
AH-241
66.61
3.81E-02
AH-241
65.61
3.54E-02
AH-241
64. OZ
3.05E-02
AM-241
60,7%
2.01E-02
AH-241
50.21
1.11E-02
AM-243
66.82
4. 59B-03
AM-243
89.22
6.88E-04
AH-243
99.6%
3.50E-05
AM-243
99.82
100.00
1.471-02
AM-241
66.91
1.45E-02
AH-241
66.61
1.38E-02
AM-241
65.62
1.2BE-02
AM-241
64. OZ
1.10E-02
AM-241
60.72
7.29E-03
AH-241
50.21
4.03E-03
AM-243
66. 81
1.6CE-03
AM-243
89.22
Z.49E-04
AH-243
99.62
1.27E-05
AM-243
99.82
200.00
5.26E-03
AM-241
66.92
5. 181-03
AM-241
66.62
4.95E-03
AM-241
65.62
4.59E-03
AH-241
64.02
3.95E-03
AM-241
60.72
2.61E-03
AM-241
50.22
1.44E-03
AM-243
66.82
5.95E-04
AM-243
89.22
8.92E-05
AM-243
99.6%
4.53E-06
AM-243
99.82
500.00
I. 321-03
AM-241
66.91
1.30E-03
AM-241
66.61
1.24E-03
AM-241
65.62
1. 15E-03
AH-241
64.02
9.891-04
AM-241
60.71
6.52E-04
AM-241
50.22
3.61E-04
AM-243
66.82
1.49E-04
AM-243
89.22
2.23E-05
AM-243
99.62
1. 13E-06
AM-243
99.82
750.00
7.02E-04
AM-241
66.92
6.91E-04
AM-241
66.62
6.60B-Q4
AM-241
65.62
6.12E-04
AH-241
64.02
5.2BE-04
AK-241
60. n
3.48E-04
AM-241
50.22
1.92E-04
AM-243
66.82
7.94E-05
AM-243
89.22
1.19E-05
AM-243
99.62
6.05E-07
AM-243
99.82
1000.00
4.46E-04
AH-241
66.92
4.40E-04
AH-241
66.62
4.20E-04
AM-241
65.62
3.89E-04
AM-241
64.02
3.35E-04
AM-241
60.72
2.21E-04
AM-241
50.22
1.22E-04
AM-243
66.82
5.05E-05
AM-243
89.22
7.57E-06
AM-243
99.62
3.85E-07
AU-243
99.82
1500.00
2.33E-04
AH-241
66.92
2.29E-04
AM-241
66.62
2.19E-04
AM-241
65.62
2.03E-04
AM-241
64. OZ
1. 75E-04
AM-241
60.71
1. 15E-04
AM-241
50.22
6.38E-05
AM-243
66.82
2.63E-05
AH-243
89.22
3.95E-06
AM-243
99.62
2.01E-07
AM-243
99.82
2000.00
1.45E-04
AM-241
66.92
1.43E-04
AM-241
S6.62
U36E-04
AM-241
55.6%
1.26E-04
AM-241
64.02
1.09E-04
AM-241
60.72
7.19E-05
AM-241
50.22
3. 971-05
AM-243
66.82
1.64E-05
AM-243
89.22
2.46E-06
AH-243
99.62
1.25E-07
AM-243
99.82
4000.00
4.41E-05
AH-241
66.92
4.34E-05
AM-241
66.62
4.15E-05
AM-241
65.62
3.85E-05
AM-241
64.02
3.32E-05
AM-241
60.72
2.19E-05
AM-241
50.22
1.21E-05
AM-243
66.82
4.99E-06
AM-243
89.22
7.48E-07
AH-243
99.62
3.80S-08
AM-243
99.82
-------
Table 5.40
Doae Equivalent Rates (rem/yr) from Breathing Air Contaminated by Radionuclides
Released by Borehole Drilling In GRANITE
7500 Years After Repository Selling
Drill Hits Repository Hater
DISTANCE (aetera)
TIME (yr)
l.OOE*01
2.00E+01
5.00E*01
l.OOE+02
2,OOE*02
5.00E+02
l.OQE+03
2.00E+03
5.00E+03
l.OOE+04
20.00
7.13E-02
AM-243
99.11
7.08E-02
AM-243
99. U
6.95E-02
AM-243
99. 2*
6.74B-02
AH-243
99.2X
6.35E-02
AM-243
99.3Z
5.30B-02
AH-243
99.6Z
3. 931-02
AH-243
99.71
2.16E-02
AH-243
99.8J
3.62E-03
AM-243
99.91
1.84E-04
AM-243
99. 9Z
50.00
1.88E-02
AH-243
99. U
1.87E-02
AH-243
99. IZ
1.84E-02
AM-243
99. 2Z
1.78E-02
AH-243
99.2%
1.68E-Q2
AM-243
99.31
1.40E-02
AM-243
99.6Z
1.04E-02
AM-243
99. 7Z
5.71E-03
AH-243
99.81
9.S7E-04
AM-243
99.91
4.87E-OS
AH-243
99. 9Z
100.00
6.62E-03
AM-243
99. IZ
6.78B-03
AM-243
99. IZ
6.66E-03
AM-243
99.21
6.46E-03
AH-243
99.21
6.08E-03
AM-243
99. 3Z
S.07E-03
AH-243
99.61
3.76E-03
AM-243
99. 7*
2.07E-03
AH-243
99,8*
3.47E-04
AH-243
99. 9*
1.76E-05
AH-243
99.91
200.00
2.44E-03
AM-243
99. «
2.43E-03
AH-243
99. IX
2.38E-03
AM-243
99. 2t
2.31S-03
AH-243
99. 2Z
2.18S-03
AM-243
99.32
1.82E-03
AH-243
99.61
1.35E-03
AM-243
99.71
7.41E-04
AM-243
99. 8Z
1.24E-04
AM-243
99. 9Z
6.32E-06
AH-243
99. 91
500.00
6.11E-04
AH-243
59. IZ
6.07E-04
AH-243
99.1Z
5.95S-04
AM-243
99. 2Z
5.78E-D4
AH-243
99.21
5.44B-04
AM-243
99. 3Z
4.54E-04
AM-243
99.6Z
3.37E-04
AM-243
99, 7Z
1.8SE-04
AH-243
99.8Z
3.10E-05
AM-243
99. 9Z
1.S8E-06
AM-243
99. 9Z
750,00
3.26E-04
AM-243
99. IZ
3.241-04
AH-243
99. IZ
3.18E-04
AM-243
99.21
3.09E-04
AM-243
99.2J
2.90E-04
AM-243
99.3Z
2.42S-04
AM-243
99.61
1.80E-04
AM-243
99. 7Z
9.89E-05
AM-243
99.81
1.66E-05
AH-243
99.9Z
8.43E-07
AM-243
99. 9Z
1000.00
2.07E-04
AH-243
99.11
2.06S-04
AM-243
99.11
2.02B-04
AH-243
99.21
1.96E-04
AM-243
99.21
1.85E-04
AM-243
99. 3Z
1.54E-04
AH-243
99. 6S
1.14E-04
AM-243
99.71
6.29E-05
AH-243
99. 8Z
1.05E-05
AH-243
99. 9Z
5.36E-07
AH-243
99. 9Z
1500.00
1.08E-04
AM-243
99. IS
1.07E-04
AM-243
99. IZ
1.05E-04
AM-243
99.22
1.02B-04
AM-243
99. 2Z
9.62E-05
AH-243
99. 3Z
8.03S-05
AM-243
99. 6Z
5.95E-05
AM-243
99. 7Z
3.28E-05
AH-243
99.BZ
5.49E-06
AM-243
99. 9Z
2.79E-07
AH-243
99, 9Z
2000.00
6.73E-05
AM-243
99. IZ
6.69B-05
AM-24S
99. IZ
6.57E-05
AM-243
99. 2Z
6.37B-05
AH-243
99. 2Z
5.99E-05
AM-243
99. 3Z
5. 001-05
AM-243
99.63
3.71E-05
AM-243
99. 7Z
2.04E-05
AB-243
99.8Z
3.42E-06
AM-243
99. 9Z
1.74E-07
AM-243
99.9%
4000.00
2.05E-05
AM-243
99. IZ
2.04E-05
AM-243
99.lt
2.00E-05
AM-243
99. 2Z
1.94B-05
AM-243
99. 2Z
1.82E-05
AM-243
99. 3Z
1.521-05
AM-243
99.61
1.13E-05
AH-243
99.7%
6.22E-06
AH-243
99. 8Z
1.04E-06
AM-243
99. 9Z
5.30E-08
AM-243
99. 9Z
-------
5.4. Release to the Aquifer due to Shaft Seal Leakage
There are four main shafts in the model repository, each with a
2
cross-sectional area of 25 m . The shafts are sealed initially to a
•3
permeability of 3.15 x 10 m/yr but degrade over 10,000 years to
31.5 m/yr. We modeled releases through one shaft from a granite
repository; the smaller amount of water in a bedded salt repository and
the tendency of the salt to seal itself make this kind of release much
less important in salt. There is no release from a granite repository
until 500 years, when the canisters fail. This model differs from the
orilling event by the greater cross-sectional area of the shaft as
compared with the borehole and the lower initial permeability. The
lower permeability counteracts, to some degree, the increased flow
area. Table 5.41 gives the annual dose rates resulting from this type
of release. The early annual dose rates, for the first 100 years, are
mainly from Sr-90. Sn-126 dominates after 100 years until some time
between 500 and 1000 years. All dose rates are small until Am-241
appears at 1000 years and gradually increase to the maximum dose rate
of 16,000 rem/yr at 10,000 years, comparable to the dose rate from
borehole drilling into a brine pocket or granite tank 1000 years after
sealing (Sections 5.1.2 and 5.1.3). Sn-126 and Tc-99 have moved far-
ther downstream. Am-241 dominates the dose rate to about 5000 years,
when Am-243 becomes dominant. Table 5.42 gives the extent of the
contaminated areas which again are roughly comparable to those from
drilling into a brine pocket or granite tank.
113
-------
IIME (yr)
l.OOE+01
2.001+01
5.00S+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
Table 5.41
Dose Equivalent Rates (rcm/yr) from Drinking Groundwater Contaminated by Radionuclides
Released from the GRANITE Repository
Shaft Seal leakage
DI STANCE (taeterg)
20.00
1.41E-05
SR -90
68,41
4,721-04
SK -90
68.71
2.24B-03
SR -90
66.01
3.42E-03
SR -90
56,21
1.21E-02
SN-126
72.0%
1.19E-01
SH-1Z6
39.01
1.191*02
AH-241
96.11
8.02E+03
AH-241
86.91
8.011*03
AH-243
91.4%
1.57E+04
AH-243
99.91
50.00
0.0
NONE
O.OZ
0.0
HONE
O.OZ
6.62E-04
SR -90
66.0%
1.551-03
SR -90
57. 1Z
1.86E-03
CS-135
40.21
3.81E-02
SN-126
79. 3*
2.331-01
SH-126
88. 3%
9.40E-01
SN-126
90.91
2.54E*03
AH-243
91.3%
7.68E+03
AH-243
99.8%
100.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
1.48E-05
SR -90
65.6%
5.52E-04
SR -90
57. 1Z
l.OOE-03
CS-135
40. 2Z
5.36E-03
CS-135
55. 6Z
9.36E-02
SH-126
80. 3Z
5.33E-01
SN-126
88. 9Z
2.82E+01
AM-243
89.0%
3.10E+03
AM-243
99. 7Z
200.00
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
0.0%
8.70E-06
SR -90
56. 5%
3.52E-04
CS-135
40,1%
2.94E-03
CS-135
58.61
1.26E-02
08-135
57. OZ
2.18E-01
SN-126
81.5%
1. 76E+00
SN-126
90.8%
4.57E+01
AM-243
87.8%
500.00
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
HONE
0.0%
8.39E-04
CS-135
58.61
5.60E-03
CS-135
60.1%
2.23E-02
CS-135
62.9%
6.05E-01
SH-126
83. 9%
2.79E+00
SN-126
91.1%
750.00
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.01',
0.0
HONE
0.0%
2.22E-04
CS-135
58.51
3.39E-03
CS-135
60.1%
1.62E-02
CS-135
62.91
2.29E-01
SN-126
66. 5 Z
1.81E+00
SN-126
89.0%
1000.00
0.0
HONE
0.0%
0.0
HONE
0.0%
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
0.0%
7.631-06
CS-135
57. 9Z
2.04E-03
CS-135
60.0%
1.24E-02
CS-135
62.9%
6. 921-02
CS-135
65. OZ
1.20E+00
SN-126
85.8%
1500.00
0.0
NONE
0.0%
0.0
NONE
0.0%
0,0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
O.OZ
5.55E-04
CS-135
60.0%
7.60E-03
CS-135
62.9%
4.79E-02
CS-135
70.6%
4.59E-01
SN-126
71. OZ
2000.00
0.0
HONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
O.OZ
1.76E-05
CS-135
SS.7%
4.64E-03
CS-135
62.9%
3.80E-02
CS-135
70.6%
1.24E-01
CS-135
72.4Z
4000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
0.0%
0.0
NOKE
0.0%
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
O.OZ
4.23E-05
CS-135
62. 7Z
1.76E-02
CS-135
70. 6Z
6.66E-02
CS-135
81.0%
-------
Table 5.42
Area (ha*) of the Aquifer Contaminated
Above the Specified Dose Rate Levels
Due to Shaft Seal Laakage
Time After Dose Levels (rem/yr)
Drilling (yr) 0.5 5 50 500
0-500 0000
1,000 0.35 0.29 0.22 0.12
2,000 0.31 0.25 0.17 0
5,000 2.2 1.4 0 0
10,000 6.6 2.9 0 0
*1 ha = 10^ square meters
115
-------
Table 5.43
Summary of Maximum Individual Annual Dose Rates
Event Type/
Pathway and,
Event time (yr)
Maximum
Dose
(rem/yr)
Nuclide Donating
Majority of Dose
And its Percentage
Drilling Hit on Waste/Aquifer
200 2000
1,000 625
3,350 51.3
7,500 23.8
Am-241
Am-241
Am-243
Am-243
Drilling into a Brine Pocket/Aquifer
200 3970 Am-241
1,000 1150 Am-241
3,350 74.3 Am-243
7,500 22.8 Am-243
Drilling into the Granite Tank/Aquifer
500 1300 Am-241
1,000 1830 Am-241
3,350 261 Am-243
7,500 66.4 Am-243
Faulting Hit on Waste/Aquifer
200 1970 Am-241
1,000 601 Am-241
3,350 36.3 Am-243
7,500 21.1 Am-243
Faulting Hit on the Granite Tank/Aquifer
200 563,000 Am-241
1,000 640,000 Am-241
3,350 83,800 Am-241
7,500 36,400 Am-243
Direct Drilling Hit on Waste/Land Surface
200 28.8 Am-241
1,000 11.2 Am-241
3,350 4.52 Pu-240
7,500 3.31 Pu-239
Drilling into a Brine Pocket/Land Surface
200 0.07 Pu-238
1,000 0.03 Am-241
3,350 0.03 Am-241
7,500 0.02 Am-243
97.7
93.1
67.5
99.7
97.7
93.1
67.5
99.6
87,0
93.1
67.5
99.8
98.8
96.5
66.6
96.2
99.1
98.2
66.3
99.4
70.7
54.2
50.4
52.7
55.0
92.3
94.2
89.3
Location and
Time of
Maximum
1000 years, 20 meters
1000 years, 20 meters
1000 years, 20 meters
1000 years, 20 meters
1000 years, 20 meters
1000 years, 20 meters
1000 years, 20 meters
1000 years, 20 meters
2000 years, 20 meters
1000 years, 20 meters
1000 years, 20 meters
1000 years, 20 meters
500 years, 4000 meters
500 years, 4000 meters
1000 years, 4000 meters
2000 years, 4000 meters
500 years, 4000 meters
100 years, 4000 meters
100 years, 4000 meters
100 years, 4000 meters
10 years,
10 years,
10 years,
10 years,
10 years,
10 years,
10 years,
10 years,
20 meters
20 meters
20 meters
20 meters
20 meters
20 meters
20 meters
20 meters
116
-------
Table 5.43 (continued)
Drilling into the Granite Tank/Land Surface
1000 0.72 Am-241 98.2
3350 0.15 An-241 66.9
7500 0.07 Am-243 99.1
Shaft Seal Leakage/Aquifer
500 1300 Am-241
95.3
10 years, 20 meters
10 years, 20 meters
10 years, 20 meters
1000 years, 20 meters
117
-------
Chapter 6
Results of the Sensitivity Analysis
In this chapter we examine the effect on annual dose rates when we
assign different values to the repository system characteristics. We
varied six parameters to study their impact on dose rates:
1. Canister Life
2. Removal of solubility limits
3. Leach rates from the canisters
4. Retardation factors in the aquifer
5. Degrading permeability of the borehole
6. Groundwater velocity
All results in this chapter are from an event occurring 1000 years
after the repository was sealed. Each event is considered in a
separate section of Chapter 6. All results are summarized in
Section 6.7. The source term and transport equations in Chapter 4 are
used in these analyses.
6.1 Effect of Varying Canister Life
In the reference case we used canister lives of 100 years for salt
and 500 years for granite. In this section we look at the effect of
changing the canister lives to 0 years (they fail immediately) and
1000 years. Changing the canister life has no effect on cases in which
canisters are destroyed either by faulting or by drilling. In cases
where the event releases repository water to the environment the
concentration of leach-limited nuclides in that water depends on the
length of time the waste has been in contact with water, and therefore
the canister life does affect these releases. Solubility-limited
nuclides are affected by canister life only when the canister remains
intact until the event, since the model considers that they reach their
solubility limits quickly.
Preceding page blank 119
-------
6.1.1 Release to the aquifer due to drilling
Granite tank
Tables 6.1 and 6.7 give the annual dose rates and the contaminated
areas, respectively, from drinking water after a drilling release to
the aquifer from repository water in granite, when canister life is
zero and the event occurs 1000 years after repository sealing.
Tables 6.2 and 6.7 present the same data for a 1000-year canister
life. The largest dose rates are 6800 rem/yr for zero canister life
and 1500 rem/yr for 1000-year life. These values may be compared with
1800 rem/yr for the 500-year canister life in Table 5.17. The peak
dose rate for the longest canister life is reached 2000 years after
drilling instead of 1000 years for the zero and 500-year canisters.
This is because the nuclides do not have as much time to leach into the
tank as they do when the canisters fail immediately. In Table 6.2 at
2COO years after drilling (3000 years since sealing) and 20 meters, the
Am-241 has been leaching for 2000 years, while in Table 6.1 the Am-241
at 1000 years after drilling (2000 years since sealing) and 20 meters
has been leaching for 2000 years also. The lower annual dose rate in
Table 6.2 is due mostly to the extra 1000 years of decay.
When we compare these doses with those from the same event with a
500-year canister life, we see that the differences are small. This is
perhaps best shown in the contaminated area results in Table 6.7. The
contaminated areas when canister life is zero are only slightly larger
than those when canister life is 500 years (Table 5.21). Increasing
canister life to 1000 years results in contaminated areas somewhat
smaller than those when canister life is 500 years. When canisters
last 1000 years, areas contaminated to a level of 0.5 rem/yr are
generally from 80 to 100% as large as the areas contaminated to this
level when canisters fail immediately. In contrast, areas contaminated
to a level of 50 rem/yr, when canisters last 1000 years, average only
60& as large as those contaminated to this level when the canisters
fail immediately.
120
-------
Brine pocket
Tables 6.3 and 6.4 show the effect of a varying canister life on
releases to the aquifer from drilling into a salt repository. The
annual dose rates throughout the tables are practically the same as
those resulting from the same event with a 100-year canister life
(Table 5.12). The amerieium isotopes, which dominate this release,
reach their solubility limit in the brine pocket very quickly. The
longer canister life yields slightly larger annual dose rates. This is
due to the term "exp[-L(t-tc)]" which can be rearranged to give
"exp(-Lt)exp(+Ltc)". The second factor increases as the canister
life, t , increases. Dose rates are below one rem/yr until Am-241
appears at a dose time of 1000 years. As the Am-241 decays, Am-243
predominates, and Sn-126 is dominant at larger distances. The
contaminated areas (Table 6.7) differ by only a few hundred square
meters; in effect they are the same. For this event, the canister life
(over the range of 0 to 1000 years) has no impact on annual dose rates
or on the extent of contamination because the americium isotopes which
are responsible for over 90% of the total dose, reach their solubility
limits quickly.
6,1.2 Release to the aquifer due to faulting
Tables 6.5 and 6.6 show annual dose rates resulting from a fault.
Table 6.5 is for a zero canister life and Table 6.6 is for a 1000-year
canister life. For a zero canister life the highest annual dose rate
occurs 100 years after the event. The value is about 630,000 rem/yr,
compared to a value of about 340,000 rem/yr for the 500-year canister
life case (Table 5.26). The longer canister life produces a con-
siderably smaller maximum dose, about 100,000 rem/yr, at a later peak
dose time, 500 years. In both cases Am-241 is the most prominent
nuclide before 5000 years while Am-243 is after 5000 years.
6.1.3 Releaseto the land surface
Table 6.8 gives the annual inhalation dose rates from a brine
pocket release to the land surface when the canisters fail immediately
121
-------
Table 6.1
TIME (yr)
l.OOE+01
2.00E+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
Dose Equivalent Rates (rem/yr) from Drinking Groundwater Contaminated by Radionuclides
Released by Borehole Drilling in GRANITE
1000 Years After Repository Sealing
Drill Hits Repository Water
Canister Life = Zero
DISTANCE (meters)
20.00
2.08E-02
CS-135
58.51
2.10E-02
CS-135
58. 71
2.13E-02
CS-135
58.31
2.60E-01
SN-126
91. 6Z
2.75E-01
SN-126
91.71
3.17E-01
SN-126
91. 8Z
6.87E+03
AM-241
93.11
2.74E+03
AM-241
76. 6Z
8.35E+02
AM-243
95.51
6.98E+02
AM-243
99.91
50.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
1.34E-02
CS-135
58.8X
1.37E-02
CS-135
58. 9Z
1.44E-02
CS-135
59. 2Z
1.89E-01
SN-126
91. 4*
2.29E-01
SN-126
91. 7Z
2.93E-01
SN-126
92. 2Z
4.46E+02
AM-243
95. 5Z
4.12E+02
AM-243
99. 9Z
100.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
9.31E-03
CS-135
58.8Z
9.57E-03
CS-135
58. 9Z
1.01E-02
CS-135
59. 2Z
1. 19E-01
SN-126
90. 4Z
1.49E-01
SN-126
91. 1Z
1.97E-01
SN-126
91. 9Z
1.63E+02
AM-243
99. 7Z
2.51E+02
AM-243
99.8:
200.00
0.0
NONE
O.OZ
0.0
NOME
O.OZ
0.0
HONE
O.OZ
6.58E-03
CS-135
58. 9Z
6.94E-03
CS-135
59. 2Z
7.91E-03
CS-135
60. 1Z
8.60E-02
SN-126
89.2:
1.25E-01
SN-126
91. OZ
1.96E-01
SN-126
92.6:
8.14E+01
AM-243
99. 7Z
500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
4.69E-03
CS-135
60. 1Z
5.59E-03
CS-135
61. 5Z
6.93E-03
CS-135
64. 2Z
1.06E-01
SN-126
91. 4Z
1.53E-01
SN-126
93. 1Z
750.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
3.61E-03
CS-135
60. 1Z
4.38E-03
CS-135
6i.s:
5.52E-03
CS-135
64.2:
7.08E-02
SN-126
89. 6Z
1.17E-01
SN-126
92. 7Z
1000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
2.92E-03
CS-135
60. 1Z
3.63E-03
CS-135
61. 5Z
4.66E-03
CS-135
64. 2X
4.33E-02
SN-126
85. 5Z
9.42E-02
SN-126
92. 1Z
1500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
2.68E-03
CS-135
61. 5Z
3.59E-03
CS-135
64. 2Z
5.02E-03
CS-135
71.8:
6.19E-02
SN-126
90. 3Z
2000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
2.05E-03
CS-135
61. 5Z
2.92E-03
CS-135
64. 2Z
4.25E-03
CS-135
71. 8Z
3.32E-02
SN-126
84.6:
4000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
1.42E-03
CS-135
64.2:
2.71E-03
CS-135
71. 8Z
3.47E-03
CS-135
81.9:
-------
Table 6.2
tIHE (yr)
l.OOE+01
2.00E+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.OOE+03
5.OOE+03
l.OQE+04
Da»e Equivalent Sates (rem/yr) from Drinking Croundwater Contatainated fcy Radionuellde*
Released by Borehole Drilling in GRANITE
1000 Years After Repository Sailing
Drill Hits Repository Water
Canister Life « 1000 years
DISTANCE (meters)
20.00
1.71E-05
1C -99
39.11
2.35E-04
CS-135
57,02
8.77E-04
CS-135
58,4%
3.10E-03
SN-126
38.3%
2.90B-02
SN-126
86.71
9.70E^02
SN-126
90.8%
3.28E+02
AH-241
93.11
1.47E+03
A»-24l
76. GZ
7.01E+02
AM-243
95, 5Z
6.56E+02
AH-243
99. n
50.00
0.0
NONE
0.02
0.0
HONE
0.0%
3.62B-04
CS-135
58. IX
1.02E-03
CS-135
58.7%
2.27E-03
CS-135
59. 1%
4.31E-02
SN-126
87.2%
1.05E-01
SN-126
90. 7Z
1.97E-01
SN-126
91.91
3.38E+Q2
AM-243
95.5%
3.81E+02
AM-243
99.91
100.00
0.0
HOME
0.0%
0.0
NONE
0.0%
2.62S-05
CS-135
52.1%
5.03E-04
CS-135
58.6%
1.40E-03
CS-135
59.1%
6.36E-03
SN-126
41.3%
5.59E-02
SH-126
87. 8Z
1.26E-01
SH-126
91.1%
3.33E+01
AM-243
98.5%
2.21E+C2
AM-243
99. 8Z
200.00
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
0.0%
3.48E-05
CS-135
55 .4Z
6.93E-04
CS-13".
59.1%
2. 408-03
CS-135
60.01
8.28E-03
SH-126
44.3%
6.88E-02
SN-126
88,7%
1.65E-01
SN-126
92. 4Z
2.77E+01
AM-243
99.11
500.00
0.0
NONE
0.02
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
O.OZ
1.02E-03
CS-135
60.0%
2.54E-03
CS-135
61,5%
4.64E-03
CS-135
64.2%
8.14E-02
SN-126
90.4Z
1.42E-01
SN-126
92.9%
750.00
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
HONE
O.OZ
0.0
NONE
O.OZ
4.75E-04
CS-135
59. 9Z
1.80E-03
CS-135
61.5%
3.608-03
CS-135
64.2%
4.55E-02
SN-126
86.1%
1.06E-01
SN-126
92.4%
1000.00
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
O.OZ
7.22E-05
CS-135
59.3%
1.3K-03
CS-135 •
61.4%
2.958-03
CS-135
64.2%
1.29E-02
SN-126
58. IZ
8.33E-02
SN-126
91.6%
1500.00
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
DOHE
O.OZ
0.0
NONE
O.OZ
6.25E-04
CS-135
61.4%
2.12E-03
CS-135
64.2%
4.271-03
CS-135
71,8%
4, 9 IE -02
SH-126
88,5%
2000.00
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
9.83E-05
CS-135
61.1%
1.571-03
CS-135
64.2%
3.57E-03
CS-135
71,8%
1.43E-02
SH-126
66.4%
4000.00
0.0
KON8
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.0!
0.0
NONE
0.0%
0.0
NONE
O.OZ
1.30E-04
CS-135
64. OZ
2.151-03
CS-135
71.8%
3.22E-03
CS-135
81,9%
-------
Table 6.3
tv
4=-
TIME (yr)
l.OOE+01
2.00E+01
S.OOEtOl
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
Dose Equivalent Hates (rem/yr) from Drinking Groundwater Contaminated by Radionuclides
Released by Borehole Drilling in BEDDED SALT
1000 Years After Repository Sealing
Drill Hits Repository Water
Canister Life » Zero
DISTANCE (meters)
20.00
3.53E-03
CS-135
58.61
3.55E-03
CS-135
58.62
3.54E-03
CS-135
58.71
4.40E-02
SN-126
92. OX
4.35E-02
SN-126
92.02
4.21E-02
SN-126
92.12
1.13E+03
AM-241
93.12
2.75E+02
AM-241
76.62
3.76E+01
AM-243
95.52
1.39E+01
AM-243
99.72
50.00
0.0
NONE
0.02
0.0
NONE
0.02
2.24E-03
CS-135
58.72
2.22E-03
CS-135
58.82
2.19E-03
CS-135
59.12
2.70E-02
SN-126
92.22
2.55E-02
SN-126
92.42
2.28E-02
SN-126
92.62
2.76E+01
AM-243
95.52
1.03E+01
AM-243
99.72
100.00
0.0
NONE
0.02
0.0
NONE
0.02
1.59E-03
CS-135
58.72
1.58E-03
CS-135
58.82
1.55E-03
CS-135
59.12
1.95E-02
SN-126
92.42
1.85E-02
SN-126
92.52
1.65E-02
SN-126
92.72
2.48E+01
AM-243
95.52
9.05E+00
AH-243
99.82
200.00
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
0.0%
1. 12E-03
CS-135
58.82
1.10E-03
CS-135
59.12
1.06E-03
CS-135
60.02
1.36E-02
SN-126
92.82
1.22E-02
SN-126
93. OX
8.73E-03
SN-126
93.62
1.04E+01
AM-243
99.92
500.00
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
0.02
6.78E-04
CS-135
60.02
6.29E-04
CS-135
61.42
5.43E-04
CS-135
64.12
6.37E-03
SN-126
94.42
3.73E-03
SN-126
94.92
750.00
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
0.02
5.60E-04
CS-135
60.02
5.20E-04
CS-135
61.42
4.49E-04
CS-135
64.12
5.84E-03
SN-126
95.02
3.37E-03
SN-126
95.32
1000.00
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
0.02
4.90E-04
CS-135
60.02
4.56E-04
CS-135
61.42
3.94E-04
CS-135
64.12
5.66E-03
SH-126
95.42
3.27E-03
SH-126
95. BZ
1500.00
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
0.02
0.0
HONE
O.OZ
3.81E-04
CS-135
61.42
3.30E-04
CS-135
64.12
2.17E-04
CS-135
71.72
3.41E-03
SN-126
96.62
2000.00
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
O.OZ
0.0
NONE
0.02
3.38E-04
CS-135
61.42
2.93E-04
CS-135
64.12
1.92E-04
CS-135
71.72
3.70E-03
SN-126
97.22
4000.00
0.0
NONE
0.02
0.0
NONE
O.OZ
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
0.02
0.0
HONE
0.02
0.0
NONE
0.02
2.28E-04
CS-135
64. 1Z
1.51E-04
CS-135
71.7Z
7.98E-05
CS-135
81.72
-------
Table 6.4
ro
en
TIME (yr)
l.OOS+01
2.00E+01
5.00E+01
l.OOE+02
2.00E+02
5.001+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
Doae Equivalent Rates (reo/yr) Iron Drinking Grouodwster Contaminated by Radionucliden
Released by Borehole Drilling in BEDDED SALT
1000 Years After Repository Sealing
Drill Hit« Repository Hater
Canister Life - 1000 years
DISTANCE (meter*)
20.00
3.91E-03
OS- 135
58.6*
3.93E-03
CS-135
58.6%
3.91S-03
CS-135
58.71
4.86E-02
SN-126
92.0%
4.811-02
SN-126
92.01
4.65E-02
SH-126
92. 1Z
1.25E+03
AH-241
93. IX
3.04E+02
AM-241
76.6%
4.15E+01
AM-243
95. 5Z
1.53B+01
AM-243
99.71
50. 00
0.0
HONE
o.oz
0.0
NONE
O.OZ
2.48E-03
CS-135
58. 7Z
2.46E-03
CS-135
58.8%
2.42B-03
CS-135
59.11
2.98E-02
SH-126
92. 2Z
2.82E-02
SN-126
92.4%
2.52E-02
SN-126
92.61
3.06E+01
AH-243
95.5%
1. 13E+QI
AM-243
99.8%
100.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
1.751-03
CS-135
58. 7X
1.74E-03
CS-135
58.8%
1.721-03
CS-135
59. 1Z
2.15E-02
SN-12fc
92.41
2.041-02
SN-126
92.51
1.82E-02
SN-126
92. 7Z
2.74E+01
AM-243
95.5%
l.OOE+01
AM-243
99.8%
200.00
0.0
HOSE
O.OZ
0.0
HONE
O.OZ
0.0
HONE
O.OZ
1.24E-03
CS-135
58.8Z
1.22E-03
CS-135
59.1%
l.UE-03
CS-135
60.0%
1.51E-02
SN-126
92.8%
1.35E-02
SH-126
93. OZ
9.651-03
SN-126
93. 6%
1. 15E+01
AH-243
99.9%
500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.0%
7.49E-04
CS-135
60. OZ
6.95E-04
CS-135
61.4%
6.00E-04
CS-135
64. 1Z
7.04E-03
SN-126
94.4Z
4.12E-03
SH-126
94. 9Z
750.00
0.0
HONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.0%
6.19E-04
CS-135
60. OZ
5.751-04
CS-135
61.4%
4.96E-04
CS-135
64. 1Z
6.46E-03
SH-126
95.01
3.73E-03
SN-126
95. 3Z
1000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
5.42E-04
CS-135
60.0%
5.04E-04
CS-135
6i. A:
4.35E-04
CS-135
64. 1%
6.26E-03
SN-126
95.4Z
3.61E-03
SH-126
95. 8Z
1500.00
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
4.211-04
CS-135
61.4Z
3.64E-04
CS-135
64.1%
2.39E-04
CS-135
71.7%
3.77E-03
SN-126
96.6%
2000.00
0.0
HONE
O.OZ
0,0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
3.74E-04
CS-135
61.4%
3.24E-04
CS-135
64. 1%
2 . 12E-04
CS-135
71. 7Z
4.09E-03
SH-126
97. 2Z
4000.00
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
2.51E-04
CS-135
64. 1Z
1.66E-04
CS-135
71. 7Z
8.82E-05
CS-135
81. 7Z
-------
cn
Table 6.5
Dose Equivalent Rates (rera/yr) froa Drinking Grouodw«ter Contaminated by Radionuclidea
Released by Fault Movement
1000 Years After Repository Sealing
Repository Water Affected
Canister Life • Zero
DISTANCE (meters)
TIME (yr)
1.0QE+Q1
2.00E+01
S.OOE-i-Ol
1.00E+Q2
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
S.OOE+03
l.OQE+04
20.00
7.30E+01
SN-126
53,91
4.83E+Q1
S8-126
88. It,
3.26E+05
AM-241
95.4%
6.32E+05
AM-241
95.11
4.30E+05
AM-241
94.4%
2.43E+05
AM-241
91. 6Z
7. 2 71+04
AM-241
84.21
2.18E+04
AM-241
55.8Z
5.84E+03
AM-243
36. OZ
2.48E+(i3
PU-239
36. a:
50.00
7.58E+01
SN-126
51.91
7.00E+01
SH-126
61. IX
3.26E+05
AM-241
95.4Z
6.32E+05
AM-241
95. 1Z
4.30E+05
AM-241
94 .«
2.43E+05
AM-241
91. 6S
1.29E+05
AM-241
84. 2 X
4.84E+04
AM-241
55. 8Z
1.08E+04
AM-243
36.0%
4.57E+03
PU-239
36.8%
100,00
7.58E+01
SN-126
51.9Z
7.00E+01
SH-126
61. IZ
3.26Et05
AM-241
95.4%
6.32E+05
AM-241
95. U
4.30E+05
AH-241
94 .4Z
2.43E+05
AM-241
91. 6%
1.29E+05
AM-241
84.21
4.84E+04
AM-241
55. 8Z
1.75E+04
AM-243
36.01
7.40E+03
WJ-239
36. 8Z
200.00
7.58E-MH
SN-126
si. n
7.00E+01
SH-126
61.1%
3.26B+05
AM-241
95.4Z
6.32E+05
AM-241
95. IZ
4.30E+05
AM-241
94. 4Z
2.43E+OS
AM-241
91.6%
1.29E+05
AM-241
84.21
4.84E+04
AM-241
55. 8Z
2.09E+04
AM-243
36.0Z
1.32E+04
PU-239
36, 8Z
500.00
7.58E+01
SN-126
51.9%
7.00B+01
SN-126
61.1%
3.26S+05
AM-241
95.4Z
6.32E+05
AM-241
95. 1Z
4. 301+05
AM-241
94.4Z
2.43E+05
AM-241
91.6%
1.29E+05
AM-241
84. 2Z
4.84E+04
AH-241
55. 8Z
2.09E+04
AM-243
35.9X
1.51E+04
PU-239
36.8%
750.00
7.58E*Ol
SN-126
51. 9%
7.00E+01
SH-126
61.1%
3.26E*05
AM-241
95. 4%
6.32E+05
AK-241
95.1%
4.30E+05
AH-241
94. 4t
2.43E+05
AM-241
91.6%
1.29E+05
AM-241
84. 2Z
4.84E+04
AM-241
55. 8Z
2.09E+04
AM-243
35.9%
1.51E+04
PU-239
36.8%
1000.00
7.58E+01
SN-126
51.9%
7.00E+01
SM-126
61.1%
3.26E+05
AM-241
95.4Z
6.32E+05
AM-241
95. IZ
4.30E+05
AM-241
94.4%
2.43E+05
AM-241
91,6%
1.29E+05
AM-241
84.2%
4.84E«-04
AM-241
55.8%
2.09E+04
AM-243
35.9Z
1.51E404
PU-239
36.8%
1500.00
7.58B+01
SH-126
51. 9Z
7.00E+01
SH-126
61.1%
3.26E+05
AM-241
95.4Z
6.32E+05
AM-241
95.1%
4.30E+05
AM-241
94.4Z
2.43E+05
AM-241
91.6%
1.29E+05
AM-241
84.2%
4.84E+04
AM-241
55.8%
2.09E+04
AM-243
35.9%
I.S1E+04
PU-239
36. 8%
2000.00
7.S8E+01
SH-126
51.9Z
7.001+01
SN-126
61.1%
3.26E+05
AM-241
95. 4Z
6.32E+05
AM-241
95.1%
4.30E+05
AM-241
94.4Z
2.43E+05
AM-241
91. 6%
1.29E+05
AM-241
84.2%
4.84E+04
AM-241
55. 8%
2.09E+04
AM-243
35. 9Z
1.51E+04
PU-239
36.8%
4000.00
7.58E+01
SN-126
51. 9Z
7.00E+01
SH-126
61.1%
3.26E+05
AM-241
95.41
6.32E+05
AM-241
95.1%
4.30E+05
AM-241
94.4%
2.43E+05
AH-241
91.6%
1.29E+05
AM-241
84.2%
4.84E+04
AM-241
55.8%
2.09E+04
AM-243
35.9%
1.511+04
PU-239
36.8%
-------
Table 6.6
TIME (yr)
l.OOE+01
2,005+01
5.00E+01
l.OOB+02
2.001+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
Dose Equivalent Rates (rea/yr) froa Drinking Groundwater Contaminated by Radionuclides
Released by Fault Movement
1000 Years After Repository Sealing
Repository Water Affected
Canister Life • 1000 years
DI STANCE (aetera)
20.00
4.52E-01
1C -99
36.5%
1.06E+00
SN-126
55.6%
4. 4 IE +02
AH-241
95. OX
3.4&E+Q4
AM-241
95.1%
7.44E+04
AH-241
94. 4Z
1.04E+05
AM-241
91.61
8.Q3E+04
AM-241
84.22
2.41E+04
AH-241
55.o4
6.45E+03
AM-243
36. OZ
2.74E+03
PU-239
3 (>.8i
50.00
4.521-Oi
1C -99
36.5%
1.24E+00
SH-126
47.9%
4.41E+02
AM-241
94.91
3.46E+Q4
AM-241
95.1%
7.44E+04
AK-241
94.4Z
1.04E+05
AM-241
91.62
8. 14E+04
AM-241
84.2%
3.96E+04
AM-241
55.8%
1.19E+04
AH-243
36. QZ
5.05E+03
PU-239
36.81
100.00
4.52E-01
TO -99
36.5%
1.24E+00
SH-126
47. 9%
4.41E+Q2
AM-241
94. SZ
3.46E+04
AM-241
95. 1Z
7.44E+04
AM-241
94. 4Z
1.04E+05
AM-241
91.62
B.14E+0-»
AM-241
84. 2Z
3.96E+04
AM-241
55. 8X
1,93F.*04
AM-243
36. OZ
8.18E+03
PU-239
36.82
200.00
4.521-01
Tl; -99
36. 5Z
1.24E+00
SS-126
47.9%
4.411+02
AM-241
94.8%
3.46E+04
AM-241
95. 1Z
7.44E+04
AM-241
94.4%
1.04E+05
AH-241
91. 6%
8.141+04
AM-241
84.22
3.96E+04
AM-241
55. 8Z
2.00E+04
AM-243
36.01
1.46E+04
PU-239
36.8%
500.00
4.52E-01
1C -99
36. 5%
1.24E+00
SH-126
47.92
4.41E+02
AM-241
94.82
3.461+04
AM-241
95. IZ
7.44E+04
AM-241
94 .4%
1.04E+05
AM-241
91.62
8. 14E+04
AM-241
84.2%
3.96E+04
AM-241
55. 8Z
2.00E+04
AM-243
35. 9%
1.52E+04
P0-239
36. 8Z
750.00
4.52E-01
TC -99
36.52
1.24E+00
SH-126
47. 9Z
4.41E+02
AM-241
94. 8%
3.46E+04
AM-241
95. IZ
7.44E+04
AH-241
94.41
1.04E+05
AM-241
91,62
8.14E+04
AM-241
84. 2Z
3.96E+04
AM-241
55. 8Z
2.00E+04
AK-243
35. 9Z
1.52E+04
PU-239
36.8%
1000.00
4.521-01
1C -99
36. 5%
1.24E+00
SH-126
47.92
4.41E+02
AM-241
94. 8Z
3.461+04
AM-241
95.12
7 .44E+04
AM-241
94.4%
1.04E+05
AH-241
91. 6%
8.14E+04
AM-241
84. 2Z
3.96E+04
AM-241
55.82
2.00E+04
AH-243
35.92
1.52E+04
PU-239
36. 8Z
1500.00
4.521-01
TC -99
36. 5Z
1.24E+00
SN-126
47.92
4.41E+02
AM-241
94. 82
3.46E+04
AM-241
95. IZ
7.44E+04
AM-241
94.4%
1.04E+05
AH-241
91.6*
8.14E+04
AM-241
84.2%
3.96E+04
AM-241
55.82
2.00E+04
AM-243
35. 9Z
1.52E+04
PU-239
36. 8S
2000.00
4.52E-01
TC -99
36.52
1.24E+00
SH-126
47.92
4.41E+02
AM-241
94.8%
3.46E+04
AH-241
95.12
7.44E+04
AM-241
94.4%
1.04E+05
AM-241
91.62
8.14E+04
AM-241
84. 2%
3.96E+04
AM-241
55. 8Z
2.00E+04
AH-243
35.92
1.52E+04
PU-239
36.81
4000.00
4.52E-01
TC -99
36. 5Z
1.24E+OQ
SN-126
47.92
4.41E+02
AM-241
94. 8Z
3.46E+04
AM-241
95. IZ
7.44E+04
AM-241
94.42
1.04E+05
AM-241
91,62
8.14E+04
AM-241
84.22
3.96B+04
AM-241
55.82
2.00E+04
AM-243
35.92
1.52E+04
PU-239
36.82
-------
Table 6.7
Area (ha*) of the Aquifer Contaminated
Above the Specified Dose Rate Levels
Because of Drilling 1000 Years after Sealing
Varying canister life
Repository type/ Length of time Dose Rate Levels (rem/yr)
Canister Life (yr)
Granite/1000
Sranite/0
Salt/1000
Salt/0
after drilling (yr)
0-500
1000
2000
5000
10000
0-500
1000
2000
5000
10000
0-500
1000
2000
5000
10000
0-500
1000
2000
5000
10000
0.5
0
0.30
0.33
2.28
7.22
0
0.37
0.34
2.59
8.03
0
0.35
0.31
2.29
6.90
0
0.35
0.31
2.27
6.79
B
0
0.23
0.27
1.47
4.08
0
0.32
0.29
1.93
5.41
0
0.29
0.25
1.51
3.53
0
0.29
0.25
1.47
3.31
50
0
0.14
0.19
0.32
0
0
0.26
0.22
0.86
0
0
0.22
0.17
0
0
0
0.22
0.16
0
0
500
0
0
0.04
0
0
0
0.17
0.11
0
0
0
0.12
0
0
0
0
0.11
0
0
0
I hectare (ha) = 10^ square meters
128
-------
fv
Table 6.8
Dose Equivalent Rotes (rcm/yr) from Breathing Air Contaminated by Radtonuclides
Released by Borehole Drilling in BEDSED SALT
1000 Years After RepoaLtory Sruiing
Drill Hits Repository Hater
Canister Life - Zero
DISTANCE (peters)
TIME (yr)
l.OQS-t-01
2.001*01
S.OOE+Ol
l.OOE+02
2.UOK+02
5.008*02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
20,00
2.91E-01
AM-241
90. IZ
2.84E-01
AM-241
90.3%
2.66E-01
AM-241
90.7%
2.40E-U1
AM-241
91. IZ
1.96S-01
AM-241
91. 3Z
1. IOE-01
AH-241
88.8%
4.44E-02
AM-241
79.9%
9.64E-03
AM-Z43
51.0%
8.35E-04
AM-243
98. 7*
4.19E-05
AM-243
100, OZ
50.00
7.68B-Q2
AM-241
90. IZ
7.52E-02
AM-241
90. 3Z
7.04E-02
AM-241
90. 7Z
6.34E-02
AM-241
91. IX
S.17E-02
AM-241
91.3%
2.90E-02
AM-241
88,8%
1.17E-02
AM-241
79. 9Z
2.55E-03
AM-243
51.0%
2.21E-04
AM-243
98, 7Z
1. UE-05
AM-243
100, OX
100.00
2.78E-02
AM-241
90. IX
2.72E-02
AM-241
90.3X
2.55E-02
AM-241
90.7%
2.30E-02
AM-241
91.151
1.87E-02
AM-241
91. 3X
1.05E-02
AM-241
88.8%
4.26E-03
AM-241
79.9%
9.23E-04
AM-243
51.0%
7.99E-05
AM-243
98.71
4.01E-06
AM-243
100. OX
200,00
9.97E-03
AM-241
90.lt
9.75E-03
AM-241
90.3Z
9.13E-03
AM-241
90. 7Z
8.22E-03
AM-241
91. IX
6. 70E-03
AM-241
91.3%
3.76E-03
AM-241
88. 8Z
U52E-03
AM-241
79. 9Z
3.30E-04
AM-243
51. OZ
2.86E-05
AM-243
98. 7%
1.44E-06
AM-243
100. OZ
500.00
2.49E-03
AM-241
90.lt
2.44E-03
AH-241
90. 3Z
2.28E-03
AH-241
90. 7Z
2.06E-03
AM-241
91. IX
1.6SB-03
AM-241
91. 3Z
9.40B-04
AM-241
88.8%
3.81E-04
AM-241
79.9%
8.26E-05
AM-243
51,0%
7.16E-06
AM-243
98.7%
3.59E-07
AM-243
100.0?
750.00
1.33B-03
AM-241
90.1%
1.30B-03
AM-241
90. 3X
1.22E-03
AM-241
90. 7X
1.101-03
AB-241
91.1%
8.95B-04
AB-241
91.32
S.02E-04
AH-241
88.8%
2.03B-04
AM-241
79.9%
4.411-05
AM-243
51.0%
3.82E-06
AH-243
98.7%
1.92E-07
AM-243
100. OX
1000,00
8.46S-04
AM-241
90. IX
8.27E-04
AM-241
90.3X
7.75E-04
AM-241
90. 7X
6.97E-04
AM-241
91, IX
5.69E-04
AM-241
91.3%
3.19E-04
AM-241
88.8Z
1.29E-04
AH-241
79. 9Z
2.80E-05
AM-243
51. OX
2.43K-06
AM-2-13
98.7%
1.22E-07
AM-243
100. OZ
1500,00
4.41E-04
AM-241
90. IX
4.31E-04
AM-241
90. 3%
4.04E-04
AH-241
90.7%
3.63E-04
AM-241
91, IX
2.96S-04
AM-241
91.31
1.66E-04
AM-241
88.8%
6.74E-05
AM-241
79. 9X
L.46E-05
AM-243
51.0%
1.27E-06
AM-243
98. 7Z
6.36E-08
AM-243
100, OZ
2000.00
2.75E-0*
AM-241
2.69E-04
AM-241
90. 3Z
2.52E-04
AM-241
90. 7Z
2.26E-04
AH-241
91.1%
1.85E-04
AM-241
71.3%
1.04E-04
AM-241
88.8%
4.20E-05
AM-241
79.9%
9.10E-05
AH-243
51.0%
7.88E-07
AM-243
98.7%
3.96E-08
AH-243
100.0%.
4000.00
8.36E-05
AM-241
90.11
8.18E-05
AM-241
90.3Z
7. 661-05
AW-241
90.7%
6.89E-05
AM-241
91.11
S.62E-05
AM-241
91.3%
3.1SE-05
AM-241
88. 8Z
1.2*8-05
AM-241
79, 9X
2.77E-06
AM-243
51. OX
2.40E-07
AM-243
98. 7Z
1.21E-08
100.0%
-------
on repository sealing and drilling occurs 1000 years after sealing.
The reason is that americium, which dominates the release, reaches its
solubility limit immediately in the small brine pocket. We do not
present a table for a 1000-year canister life since if the event time
is 1000 years, and the canister life 1s also 1000 years, the release of
a brine pocket to the land surface would bring with it no contami-
nation, since no waste would have escaped the intact canister.
6.2 Effect of No Solubility Limits
In this section we examine the effect of assuming that all
nuclides have unlimited solubility, and their entry into groundwater is
limited by the leach rate only. Since solubility limits apply to Tc,
Np, and Pu (and Am in brine pocket releases), the effects of these
nuclides will be greater when there are no solubility limits. The
doses from other nuclides do not change.
6.2.1 Release to the aquifer due to drilling
Direct hit on waste
Table 6.9 gives the annual dose rates from a direct hit at 1000 years.
It is the same time and event as described in Table 5.7, except for the
removal of solubility limits. Tc-99 has replaced Cs-135 as the
dominant nuclide up to a dose time of about 50 years. At a dose time
of 500 years, Sn-126 has moved 105 meters and is the largest con-
tributor between 0 and 10P meters. Ara-241 appears at 20 meters and
1000 years where the dose is 690 rera/yr; the dose rate from the Am-241
is the same in both tables since it is not limited by solubility. Most
of the difference in dose rate, about 65 rem/yr, is contributed by
Plutonium; Sn-126 and Tc-99 are farther downstream. By 5000 years, the
Am-241 has decayed enough so that the Am-243 is dominant to about
100 meters. Pu-239 becomes prominent at 10,000 years after the
drilling, when the amount of Am-243 has been reduced by decay. In
contrast, Table 5.7 shows that Am-243 contributes virtually all of the
10,000-year dose. The presence of Pu-239 in the aquifer makes the
contamination last much longer. Comparing the area tables 5.11 and
6.16, we see that the results are nearly the same for about 2000 years.
130
-------
Table 6.9
Dote Equivalent Rates (rea/fr) from Drinking Grounduatet Contaminated by Radionuclideo
Released by Borehole Drilling
1000 Years After Repository Sealing
Drill Hits Wsste
TIME (yr)
l.OOE+01
2.00E+01
5.00E+01
l.OOE+02
2.00E+02
5.0QE+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
Ho Hue 1 ides Limited by Solubility
DISTANCE (ttetert)
20.00
4.09E-03
1C -99
52.21
4.09E-03
TC -99
52. n
4.071-03
TC -99
52. n
2.63E-02
SN-126
84. 6%
2.61E-02
SH-126
84.7%
2.52E-02
SH-126
84.7%
6.91E+02
AH-241
84. 2%
2.08E+02
AM-241
55.81
5.56E+01
AM-243
36.0%
2.36E+01
PU-239
36.8?
50.00
0.0
HONE
Q.0%
0.0
HONE
0.0%
2.58E-03
TC -99
52.2Z
2.56E-03
TC -99
52.31
2.53E-03
TC -99
52.4%
1.61E-02
SH-126
84.9%
1.53E-02
SH-126
85.0%
1.37E-02
SN-126
85.21
4.05E+01
AH-243
36.0%
1.72E+01
IU-239
36. 8Z
100.00
0.0
NOME
0.02
0.0
NONE
O.OZ
1.83S-03
TC -99
52.2Z
I. B2E-03
TC -99
52.31
1.79E-03
TC -99
52.4Z
1. 17E-02
SN-126
85. 2X
l.iOE-02
SN-126
83.3*
9.89E-03
SN-126
85.51
3.64E*01
AH-243
36. OX
1.54E+01
TO- 239
36.8:
200.00
0.0
NONE
0.02
0.0
NONE
0.0%
0.0
NONE
0.0%
1.29E-03
TC -99
52.33?
1.28E-03
TC -99
52.4%
U23E-03
TC -99
52.7%
8.13S-03
SH-126
85. 8Z
7.29E-03
SH-126
86. OZ
5.27E-03
SH-126
86.41
1.75E+01
PU-239
36.8%
500.00
0.0
HONE
O.OZ
0.0
NONE
0.0%
0.0
HONK
0.0%
0.0
HONS
O.OZ
0.0
NONE
O.OZ
T.88E-04
TC -99
52.7%
?.41E-04
TC -99
53. 3Z
6.56E-04
TC -99
54. 3Z
3.78E-03
SH-126
87.8%
2.21E-03
SH-126
88.21
750.00
0.0
noire
O.OZ
0.0
HOKE
0.0%
0.0
noire
0.0%
0.0
HOKE
0.0%
0.0
NOHE
0.0%
6.518-04
TC -99
52, 7Z
6.12E-04
TC -9>
53.3%
5.42E-04
TC -99
54. 3Z
3.43E-03
SN-126
88.91
2.00E-03
SH-12S
89.2%
1000.00
0.0
NONE
O.OZ
0.0
HONE
0.0%
0,0
NOW
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
5.7IE-04
1C -99
52.7%
5.36E-04
TC -99
53. 3Z
4.75E-04
TC -99
54. 3*
3.31E-03
SN-126
89.91
1.931-03
SN-126
90.2Z
1500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.Kt
4.49E-04
TC -99
53.3%
3.97E-04
TC -99
54.31
2.7BE-04
TC -99
56. 8%
1.97E-03
SN-126
92,0*
2000.00
0.0
HOME
O.OZ
0.0
NONE
O.OZ
0.0
NOKE
O.OZ
0.0
NOHE
O.OZ
0.0
HOKE
O.OX
0.0
HOHE
O.OZ
3.98E-04
TC -99
53.3%
3.52E-04
TC -99
54. 3Z
2.47E-04
TC -99
56. 8Z
2.13E-03
SH-126
93.4%
4000. 00
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
HONE
O.OZ
0.0
HONE
0.0%
0.0
Non
O.OZ
0.0
NONE
0.0%
2.74E-04
TC -99
54.31
1.92E-04
TC -99
56. a:
1.09E-04
TC -99
59.61
-------
Penetration Into contaminated repository water
Table 6.10 gives the annual dose rates from drinking aquifer water
after a drill penetrates a contaminated granite strata (granite tank)
when there are no solubility limits. Table 5.17 gives the results for
this event with solubility limits. Tc-99 dominates the early portion
in Table ti.10, as compared to Cs-135 in the solubility-limited case.
The early dose rates in Table 6.10 are about a factor of two higher
than those in Table 5.17; at 50 years the maximum dose rate (Table 6.10)
is about 0.02 rem/yr. Between 100 and 500 years, Sn-126 is the
dominant nuclide while Tc-99 is more important downstream beyond the
Sn-126. Am-241 is dominant from 1000 to 2000 years. The annual dose
rates for these times in Table 6.10 are higher than those in Table 5.17
because of some contribution from Pu-239. At 5000 years, Am-243
contributes about 36% of the total of 2000 rem/yr or 720 rem/yr. At
5000 years with solubility limits, the 131 rem/yr from the Am-243 is
95.5% of the total 137 rem/yr. The additional 1850 rem/yr in
Table 6.10 is the contribution of solubility-limited nuclides,
especially plutonium nuclides. At 10,000 years, Pu-239 is the dominate
nuclide in Table 6.10, compared to Am-243 in the base case. At the
10,000-year dose time, the Pu-239 provides a maximum dose of
2000 rem/yr.
Tables 5.21 and 6.16 give the areas contaminated by the release
with and without solubility limits. The areas contaminated are about
the same for both cases until 10,000 years, when they are slightly
larger without solubility limits than with solubility limits. The lack
of solubility limits increases the time for potential contamination.
Tables 5.12 and 6.11 give results for drilling releases from a
brine pocket to the aquifers. In Table 5.12 some nuclides are
solubility-limited, however, in Table 6.11, they are leach-limited.
The annual dose rates for brine pocket releases in Table 6.11 are
somewhat smaller than those for granite tank releases in Table 6.10;
the maximum dose rate in Table 6.10 is about 4000 rem/yr whereas in
Table 6.11 it is near 1300 rem/yr and in Table 5.12 it is 1100 rem/yr.
132
-------
Table 6.10
TIME(yr)
l.OOE+01
2.0QE+01
5.00E+01
l.OOE+02
2.001+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
Qose Equivalent Rates (re»/yr) from Drinking Groundwater Contaminated by Radionuclides
Released by Borehole Drilling in GRANITE
1000 Years After Repository Sealing
Drill Hitt Repository Hater
Ho Nuclidea Limited By Solubility
DISTANCE (meters)
20.00
2.23E-02
TC -99
52.21
2.27E-02
TC -99
52.2*
2.37E-02
TC -99
52. 2Z
1.48E-01
SH-126
32.81
1.70E-01
SN-126
83.11
2.29B-01
SN-126
83. 7*
4.07E+03
AM-241
84.21
2.9214-03
AM-241
55. 8%
2.04E+03
AM- 243
36.01
2.07E+03
PU-239
36. SI
50.00
0.0"
NOME
0.0!
0.0
KOBE
0.0!
1.47E-02
TC -99
52. 2Z
1.58E-02
TC -99
52,31
1.7SE-02
TC -99
52.4*
1.30E-01
SN-126
82.12
1.85E-01
SN-126
83.31
2.69E-01
SN-126
84.2*
1.04E+03
AH-243
36.01
1.21E-HJ3
PU-239
36.81
100.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
l.QOE-02
TC -99
52.2*
1.08E-02
TC -99
52. 3Z
1.23E-02
TC -99
52. 4Z
7.25B-02
SN-126
77.61
1.15E-01
SB- 126,
81.2Z
1.79E-01
SN-126
83. 3Z
2.76E+02
AM-243
35.9%
7.22E+02
PU-239
36.82
200.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
7.09E-03
TC -99
52.3Z
8.18K-03
TC -99
52 .4%
1. 10E-02
TC -99
52. 7Z
5.611-02
SB- 126
73. 3Z
1.09E-01
SN-126
80.81
1.99E-01
SH-126
84. 2Z
1.68E+02
PU-239
36. 7Z
500.00
0.0
KOBE
O.OZ
0.0
HONE
O.OZ
0.0
NOME
O.OZ
0.0
HONE
o.ox
0.0
NONE
O.OZ
6.14E-03
TC -99
52. 7Z
8.77E-03
TC -99
53.3X
1.27E-02
TC -99
54. 3Z
1.05E-01
SK-126
81.3Z
1.63E-01
SN-126
84. 3Z
750.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.01
0.0
NONE
O.OZ
0.0
NONE
O.OZ
4.40E-03
TC -99
52. 7Z
6.68E-03
TC -99
53. 3Z
l.OOE-02
TC -99
54. 3%
6.74E-02
SN-126
76.5*
1.24E-01
SN-126
83.41
1000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
D.OZ
0.0
NONE
O.OZ
3.24E-03
TC -99
52.7%
5.34E-03
TC -99
53. 3Z
8.37E-03
TC -99
54. 3Z
3.61E-02
SN-126
62. 5Z
9.95E-02
SN-126
82. 1Z
1500.00
0.0
NONE
O.OZ
0.0
HONK
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
3.59E-03
TC -99
53. 3Z
6.291-03
TC -99
54. 3%
1.08E-02
TC -99
56.81
6.42E-02
SN-126
77.61
2000.00
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
KONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
2.34E-03
TC -99
53. 3Z
4.94E-03
TC -99
54. 3Z
9.08E-03
TC -99
56.8%
3.13B-02
SN-126
60. 7Z
4000. OD
0.0
NONE
O.OZ
0.0
NONE
o.oz
0.0
NONE
O.OZ
0.0
NONE
O.OZ
Q.O
NONE
0.0!
0.0
NONE
O.OZ
0.0
NONE
O.OZ
1.73E-03
TC -99
54. 3Z
5.64E-03
TC -99
56.8Z
B.29E-03
TC -99
59. 6Z
-------
fable 6.U
TIME (yr)
l.OOE+Ol
2.00B+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
1.QQE+Q3
2.00E+03
S.OOE+03
1,001+04
Dose Equivalent Rates (res/ye) from Drinking Groundwater Contaminated by Radionuclidea
Released by Borcho'o Drilling in BEDDED SALT
1000 Years After Repository Sealing
Drill Hies Repository Hater
No Nudities Limited by Solubility
DISTANCE (meters)
20.00
7.45E-Q3
TC -99
52.21
7.501-03
TO -99
52. 2Z
7.48E-03
TC -99
52. 2Z
4.83E-02
SN-126
84.61
4.78E-02
SN-126
84.72
4.62E-02
SN-126
84.72
1.27E+03
AB-241
84.22
3.81E+02
AM-241
55.81
1.01E+02
AM-243
36.01
4.27E+01
CTJ-239
36.8!
50.00
0.0
NONE
o.oz
0.0
NONE
0.02
4.73E-03
TC -99
52.2%
4.70E-03
TC -99
52. 31
4.63E-03
TC -99
5Z.4I
2.96E-02
SN-126
84.9*
2.80S-02
SN-126
85. OZ
2.51E-02
SH-126
85. IS
7.42E+01
AH-243
36. OZ
3.16E+01
Hf-239
36. 8%
100.00
0.0
NONE
o.oz
0.0
NONE
O.OZ
3.351-03
TC -99
52. 2*
3.33E-03
TC -99
52,3%
3.29E-03
TC -99
52. 4Z
2.16E-02
SN-126
85. 2Z
2.02E-02
SB-126
85. 3%
1.81E-02
SN-126
85.3Z
6.66E*Ol
AH-243
36. OZ
2.79E+01
PU-239
36. BZ
200.00
0.0
HONE
O.OZ
0,0
NONE
O.OZ
0.0
NONE
O.OZ
2.37E-03
TC -99
52.31
2.34E-03
TC -99
52,42
2.25E-03
TC -99
52. 7Z
1.49E-02
SN-126
85.81
1.34E-02
SM-U6
85. 9Z
9.56E-03
SN-126
86.3!
3.21E+01
PU-239
36.81
500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
1.45E-03
TC -99
52.71
1.368-03
TC -99
53. 3Z
1.20E-03
TC -99
54. 3Z
6.91E-03
SI- 126
87.9Z
4.05E-03
SH-126
88. 2 J
750.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.02
0.0
NONE
O.OZ
1. 191-03
TC -99
52. 7Z
I. 121-03
TC -99
53. 3Z
9.91E-04
TC -99
54.3%
6.29S-03
SN-126
89. 1Z
3.64E-03
SH-126
89.22
1000.00
0.0
HOHE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OX
1.05E-03
TC -99
52. 7Z
9.84B-04
TC -99-
53.32
8.68E-04
TC -99
54.32
6.061-03
SN-126
90.0Z
3.50E-03
SN-126
90. 2Z
1500,00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0,02
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
B.22B-04
1C -99
53. 3Z
7.27E-04
TC -99
54. 3Z
5.05E-04
1C -99
56. 8Z
3.611-03
SH-126
92. 1Z
2000,00
0.0
NONE
O.OZ
0.0
NONE
0.02
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
HONK
0.02
7.29E-04
TC -99
53. 3Z
6.46E-04
'TC -99
54.32
4.48E-04
TC -99
56.8Z
3.89E-03
SN-126
93.52
4000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0,0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
O.OZ
5.021-04
TC -99
54. 3Z
3.52E-04
TC -99
56.82
1.99E-04
TC -99
59.62
-------
Once again Tc-99 and Sn-126 are the dominant nuclides at all distances
until 1000 years after the drilling occurred. We then see the
americium isotopes dominating the closer distances (up to 100 m) until
Pu-239 takes precedence at 10,000 years and up to 200 m. This is the
same pattern followed in Table 5.12 except that Am-243 maintains
dominance at 10,000 years.
6.2.2 Release to the aquifer due to faulting
Direct hit on waste
Table 6.12 shows the results of a fault line through waste from,
or in, a row of waste canisters without solubility limits on the
nuclides. The comparable data with solubility limits are in
Table 5.22. The same nuclides, Sn-126, Am-241, and Am-243, dominate
until a dose time of 10,000 years when Pu-239 has replaced Am-243 as
the major contributor to the total dose rate. The peak dose rates in
Tables 5.22 and 6.12 are near 600 rern/yr and both occur 500 years after
the event. Furthermore, other values in the tables are similar—which
implies that the presence or absence of solubility limits does not
affect releases in this scenario.
Granite tank
The results of the faulting event are presented in Table 6.13; the
same event with solubility limits is given in Table 5.26. In the first
20 years after the event, Sn-126 is the dominant isotope and the annual
dose rates are almost two times higher. Am-241 dominates both tables
from 50 years through 2000 years. The dose rates, assuming no solu-
bility limits, converge with those with solubility limits until
5000 years. At 5000 years, Am-243 dominates the entire length studied
but other nuclides, particularly plutonium isotopes, also contribute
significantly. At 10,000 years, Pu-239 dominates both tables when the
americium isotopes have decayed to lower levels. The removal of the
solubility limits in this scenario has increased the annual dose rates
by, at most, a factor of two.
135
-------
CO
01
TIME (yr)
l.OOE+01
2.00E+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.ODE+03
5.00E+03
l.OOE+04
table 6.12
Dose Equivalent Rates Crem/yr) from Drinking Groundwater Contaminated by Radionuclides
Released by Fault Movement
1000 Years Alter Rapoaitory Sealing
Waste Directly Affected
No NucliUee Limited by Solubility
pISTAHCE (aeterg)
20.00
5.4 IE -03
SH-126
41.42
8.39E-03
SN-126
62. 2Z
1.41E+01
AM-241
95. 3%
2.37E+02
AM-241
95. IZ
4.72E+02
AM-241
94.4%
6.33E+02
AM-241
91. 6%
4.69E+02
AM-241
84. 2Z
1.41E+02
AM-241
55.8%
3.77E+01
AM-243
35. OX
1.60E+01
PU-239
36,91
50.00
5.51E-03
SH-126
40.62
1.02E-02
SH-126
51.01
1.41E+01
AM-241
95,3%
2.37E+02
AM-241
95.1%
4.73E+02
AM-241
94.4%
6.33E+02
AM-241
91.61
4.S3E+02
AM-241
84. 2%
2.15E+02
AM-241
55. 8X
6.27E+01
AM-243
36. OS
2.66E+01
PU-239
36.81
100.00
5.51E-03
SS-126
40.6%
1.02E-02
SN-126
51.01
1.41E+01
AH-241
95.31
2.37B+Q2
AM-241
95. IX
4.73E4-02
AM-241
94.4%
6.33E+02
AM-241
91.6%
4.83E+02
AH-241
84. 2Z
2.15E+02
AM-241
55. 8Z
8.61E+01
AM-243
36.0%
3.65E+01
PU-239
36. 8Z
200.00
5.51B-03
SH-126
40. 6t
1.02E-02
SN-126
51.0Z
1.41E*Ol
AM-241
95.31
2.37E+02
AM-241
95. IZ
4.73E+02
AH-241
94.4X
6.33E402
AM-241
91. 6Z
4.83E+02
AM-241
84. 2Z
2. 15E+02
AM-241
55.8%
8.78E+01
AH-243
35.9%
4.65E+01
PU-239
36. 8Z
500.00
5.51B-03
SN-126
40. 6%
1.02E-02
SN-126
51. OZ
1.41B+01
AM-241
95. 3Z
2.37E+02
AHr24l
95. IZ
4.73E-»02
AH-241
94.4%
6.33E+02
AM-241
91.6Z
4.83E+02
AM-241
34. ZZ
2.15E+02
AM-241
55. 8Z
8.79E+01
AM-243
35. 9Z
4. 7 IE +01
PU-239
36.8%
750,00
5.51E-03
SH-126
40.6%
1.02E-02
SN-126
51.0Z
1.41E+01
AM-241
95. 3%
2.37E+02
AH-241
95. IZ
4.73E+02
AM-241
94. 4Z
6.33E402
AM-241
91.6%
4.83E*02
AM-241
84. 2Z
2.15E*02
AH-241
55. 8Z
8, 79E+01
AM-243
35. 9Z
4.71E+01
PU-239
36. 8Z
1000.00
5.51E-03
SH-126
40.6%
1.02E-02
SH-126
51. OZ
1.41E+01
AM-241
95. 3Z
2.3?E*02
AH-241
95. IS
4.73E+02
AH-241
94,4%
6.33E+02
AM-241
91. 6Z
4.83E-I-02
AM-241
84.21
2.15E+02
AM-241
55. 8S
8.79E+01
AM-243
35. 9Z
4.71E+01
PU-239
36.8%
1500.00
5.51E-03
SH-125
'i 0.61
1.02E-02
SN-126
51.01
1.41E4-01
AM-241
95.3%
2.37E+02
AM-241
95.1%
4.73E+02
AM-241
94.4%
6.33E402
AM-241
91.61
4.83E+02
AM-241
84. 2%
2.15E+02
AM-241
55.8%
8.79B+01
AM-243
35.9%
4.71E+01
PU-239
36.8%
2000.00
5.51E-03
SK-126
40. 6Z
1.02E-02
SH-126
51.0%
1.41E+01
AM-241
95.3Z
2.37E+02
AM-241
95.1%
4.73E+02
AK-241
94.4Z
6.33E+02
AH-241
91.6%
4.83E+02
AM-241
84.2%
2.15E+02
AM-241
55. 8Z
8.79E*01
AM-243
35. 9%
4.71E+01
PU-239
36.7%
4000.00
5.51B-03
SH-126
40.6%
1.02E-02
SN-126
51.0%
1.41E+01
AM-241
95.3%
2.37E+02
AM-241
95. IZ
4. 73E+02
AH-241
94.4%
6.33E+02
AH-241
91. 6Z
4.83E+02
AM-241
84.2%
2.15E*02
AM-241
55. 8Z
8.79E+01
AM-243
35. 9Z
4.71E-f01
PU-239
36. 7Z
-------
Table 6,13
OJ
TIMS(yr)
i.OOE+Ol
2.00E+01
5.00E+01
1.00E-t02
2.00E+02
5.00E+02
l.OOE+03
2.QOE+Q3
5.0GE+Q3
l.OOE+04
Dose Equivalent Rates (rea/yr) from Drinking Groundwater Contaminated by Radionuc Hdes
Released by Fault Movement in GRANITE
1000 Years After Repository Sealing
Repository Water Affected
Ho HueIides Limited by Solubility
(meters)
20.00
6.61E+01
SN-126
53,92
4.38E+Q1
SN-126
88.6*
2.95B+05
AM-241
95.4Z
5.7SE+05
AM-241
95.1*
3.96E+05
AM-241
94.41
2.30E+05
AH-241
91. 61
7.34E+04
AM-241
84.22
2.21E+Q4
AM-241
55.82
5.90E+03
AM-243
36. 01
2.50E+03
PB-2J9
36.81
50,00
6.86E+01
SN-126
51,92
6.33E+01
SN-126
61.2%
2.95E+Q5
AM-241
95.42
5.75E+05
AM-241
95. IS
3.96E+05
AK-241
94.4*
2.30E+05
AM-241
91. 65!
1.24E+05
AH-241
84. 22
4.76E+04
A»-241
55. BZ
1.09E+04
AM-243
36.01
4.62E+03
PU-239
36. 8X
100.00
6.86E+01
SM-126
51. 9Z
6.33E+01
SM-126
61.2!
2.95E+05
AM-241
95. 4X
5.75E+05
AM-241
95. IX
3.96KW5
AM-241
94.4X
2.30E+05
AM-241
91. 6Z
1.24E+05
AM-241
84.21
4.76E+04
AM-241
55. 8Z
1.76E+04
AH-243
36.01
7.48E+03
PU-239
36. 8X
200.00
6.86E+01
SH-126
51,9%
6.33E*01
SN-126
61.21
2,951*05
AM-241
95.4Z
5.75E*05
AM-241
95. IZ
3.961+05
AM-241
94.4%
2.30E+05
AM-241
91.6%
1.24E+05
AM-241
84. 2Z
4.76E+04
AM-241
55. 8Z
2.08E+04
AM-243
36. OZ
1.33E*04
PU-Z39
36. BZ
500,00
6.86E+01
SH-126
51. 9Z
6.33E*01
SH-126
61. 2%
2.95E+05
AM-241
95.4X
5.75E*05
AM-241
9S.1Z
3.96Et05
AM-2H
94.41
2.30E+05
AM-241
91.6%
1.24E+05
AM-241
84.22
4.76E+04
AW-241
55.81
2.08E+04
AM-243
35.91
1.51E+Q4
FU-239
36.81
750.00
6.86E-I-DI
SN-126
51. 9X
6.331+01
SN-126
61. 2S
2.95B+05
AM-241
95.4Z
5.75B+05
AM-241
95. 11
3. 96B+05
AM-241
94.4%
2.30B+05
AM-241
91. 6X
1.24E+05
AM-241
84.2Z
4.76E+04
AM-241
55. 8X
2.08E+04
AM-243
35.91
1.51E+04
FU-239
36.8?
1000.00
6.86E+Q1
SH-126
51.9Z
6.33E+01
SN-126
6X.2Z
2.95B+OS
AM-241
95.42
5.75E+05
AM-241
95. 1J
3.961+05
AM-241
94.4Z
2.30E+05
AM-241
91. 6t
1.241*05
AM-241
84.21
4.76E+04
AH-241
55.82
2.09E+04
AM-243
15.91
1.51E+04
PO-239
36.8Z
1500.00
6.86E+01
SM-126
51.92
6.33S+01
SH-126
61.22
2.95S+05
AH-241
95.42
5.751+05
AM-241
95.12
3.96E+05
AM-241
94.42
2.30E+05
AM-241
91.62
1.24B+05
AM-241
84.22
4.76E+04
AM-241
55.82
2.09E+04
AM-243
35.92
U51E+04
PU-239
36.82
2000.00
6.86E+Q1
SN-126
51.92
6.33E+01
SH-126
61.22
2.95E+05
AM-241
95.4J
5.75E+05
AM-241
95.12
3.96E+05
AM-241
94.42
2.30E+05
AM-241
91.62
1.24E+05
AH-241
84.22
4.76E+04
AM-241
55.82
2.09E+04
AM-243 "
35,92
1.51E+04
PB-Z39
36,82
4000.00
6.86E+01
SN-126
51.92
6.33E+01
SH-126
61,22
2.95E+05
AM-241
95.42
5.75E+05
AM-241
95.12
3.96E+05
AM-241
94.42
2.30E+05
AM-241
91.61
1.24E+05
AM-241
84.22
4.76E+04
AM-241
55.82
2.09E+04
AM-243
35.92
1.51E+04
PU-239
36.82
-------
6.2.3 Release to the land surface
Table 6.14 gives the annual dose rates resulting from breathing
air contaminated by release to the land surface from a drill puncturing
a brine pocket around two canisters, assuming no solubility limits.
The doses in Table 6.14 are much higher than those for the similar case
with solubility limits (Table 5.34), the highest being 22 rem/yr
compared with 0.02 rem/yr in the base case. There are two reasons for
this increase. First, the annual dose rates from Am-241, are larger by
a factor of about 20 because americium solubility is limiting in the
base case. Second, other nuclides, such as plutonium isotopes and
technetium, which are solubility-limited in the base case, are released
here. After 1000 years, Pu-239 and -240 dominate the doses. Areas
contaminated above 0.5 rem/yr are presented on Table 6.16; they are all
less then one ha. In the base case, there were only small areas above
0.5 rem/year.
6.2.4 Release to the aquifer due to shaft seal leakage
The annual dose rates in Table 6.15 and the contaminated areas
(refer to direct hit drilling in Table 6.16) are about the same as
those of Tables 5.41 and 5.42, respectively. The removal of the
solubility limits has caused the annual dose rates in Table 6.15 to
increase only slightly above those of Table 5.41. The contaminated
areas in the base case are about the same.
6.3 Effect of Varying the Leach Rate
The base case assumed a leach rate of 10 yr" . In this
chapter, we examine the effect of varying this leach rate. Values
SI -21
examined range from 10 yr to 10 yr . A higher leach rate
would cause radionuclides (except those whose concentrations are
limited by solubility) to enter the environment more quickly, and dose
rates from them would be higher. This would be true for all releases
from brine pockets and from the granite tank water, except for direct
hit releases to the land surface. Since rapid leaching would deplete
138
-------
Table 6,14
OJ
TIME (yr)
l.OOB+01
2.00E+01
5.00E+01
l.OOE+02
2.001*02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
Dose Equivalent Rates (ren/yr) from Breathing Air Contaminated by Rsdionuclidefl
Released by Borehole Drilling in BEDDED SALT
1000 Years After Repository Sealing
Drill Hit« Repository Water
No Nucliripa Limited By Solubility
DISTANCE {meters)
20.00
2.21E+01
AM-241
53.9%
2.18E+01
AM-241
53.51
•2.09E+01
AM-241
52.5%
1.96E-MU
AH-241
50.7%
1.72E+01
AH-241
47.1%
1.21E+01
AM-241
36.61
7.36E+00
FU-240
43.4%
3.44E+00
PU-240
50.5%
5.80E-01
PU-239
49.3%
3.40E-U7
PU-239
58.3%
50.00
5.84E+00
AM-241
53.9%
5.76E+00
AM-241
53.5%
5.53S+00
AH-241
52.5%
5.17S+00
AM-241
50.7%
4.55B+00
AM-241
47.11
3.19EWO
AH-241
36.6%
1.94E+QO
PU-240
43.4%
9.10E-01
PU-240
50.5%
1.53E-01
PU-239
49,3%
8.98E-03
PU-239
58.3%
100.00
2.11E+00
AM-241
53.91
2.09E+00
AM-241
53.5%
2.00E+00
AM-241
52.51
1.87E+00
AM-241
50.7%
1.65B4-00
AB-241
47. IX
1. ISE-t-OO
AH-241
36.6%
7.041-01
PU-240
43.4%
3.30E-01
PU-240
50. 5Z
5.55E-02
PU-239
49. 31
3.25E-03
PU-239
58.3%
200.00
7.57E-01
AM-241
53.9%
7.46E-01
AM-241
53.5%
7.17E-01
AM-241
52.5%
6.71E-01
AM-241
50.7%
5.90E-01
AH-241
47.1%
4.14E-01
AM-241
36.6%
2.52E-01
PU-240
43.4%
1.18E-01
PU-240
50.5%
1.99E-02
PU-239
49.3%
1. 16E-03
PU-239
58.3%
500.00
1.89E-01
AW-241
53.9%
1. 87E-01
AM-241
53.5%
1.79E-01
AM-241
52.5%
1.68E-01
AM-241
50.7%
1.48E-01
AM-241
47.1%
1.04E-01
AM-241
36.6%
6.31E-02
PU-240
43.4%
2.95E-02
PU-240
50.5%
4.97E-03
PU-239
49. 3%
2.91E-04
PU-239
58.3%
750.00
1.01E-01
AM-241
53.9%
9.96E-02
AM-241
53.5%
9.57E-02
AM-241
52.5%
8.95E-02
AM-241
50.7%
7.88E-02
AH-241
47.1%
5.53E-02
AH-241
36.6%
3.37E-02
PB-240
43.41
1.58E-02
PU-240
50.5%
2.65E-03
TO-239
49.3%
1.55E-04
PU-239
58.3%
1000.00
6.42E-02
AM-241
53.9%
6.331-02
AM-241
53.5%
6.08E-02
AM-241
52.5%
5.69E-02
AM-241
50.7%
5.01E-02
AM-241
47.1%
3.51E-02
AM-241
36.6%
2.14E-02
PO-240
43.4%
l.OOE-02
PU-240
50.51
1.69E-03
PU-239
49.3%
9.88E-05
PU-239
58.3%
1500.00
3.35E-02
AM-241
53.9%
3.30E-02
AH-241
53.5%
3.171-02
AM-241
52.52
2.97E-02
AM-241
50.72
2.611-02
AM-241
47.1%
1.83E-02
AM-241
36.6%
1.12E-02
PU-240
43.4%
5.22E-03
PU-240
50.5%
8.79E-04
PU-239
49.3%
5.15E-05
PU-239
58. 3X
2000.00
2.09E-C2
AM-241
53.92
2.05S-02
AM-241
53.51
1.98E-02
AM-241
52.52
1.85E-Q2
AM-241
50.71
1.63E-02
AM-241
47.1%
1.14E-02
AM-241
36.6%
6.95E-03
PU-240
43.4%
3.25E-03
PU-240
50.5%
5.48E-04
PU-239
49.3%
3.21E-05
PU-239
58.3%
4000.00
6.35E-03
AM-241
53.9%
6.26E-03
AH-241
53.5%
6.01E-03
AM-241
52.52
5.63E-03
AM-241
50. 7Z
4.95E-03
AH-241
47.1%
3.47E-03
AM-241
36.61
2.11E-03
PU-240
43.42
9.90E-04
PU-240
50.5%
1.67E-04
PU-239
49.3%
9.77E-06
PU-239
58.3%
-------
Teble 6.15
2.00E+01
5.00E+Q1
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
Dose Equivalent Rates (ree/yr) from Drinking Grojndwater Contaminated by Radionuclides
Released by Shaft Seal Leakage in GRANITE
No Huclide* Limited by Solubility
DISTANCE (meters)
20.00
8.50E-06
SR -90
67. 7Z
2.89E-04
SH -90
66.61
1.406-03
SB -90
62.01
2.341-03
SR -90
47.4J
8.32E-03
SH-126
60.22
6.92E-02
SN-126
79.91
7,328+01
AM-241
91.3*
4.14E+03
AM-241
72,11
4.14E403
AM-243
35.7%
2.391+03
FO-239
36,11
50.00
0.0
HONE
O.OZ
0.0
HONE
0.0%
4.16B-04
SR -90
62. OZ
1, 07E-03
SR -9O
48. IX
1.82E-03
TC -99
42.81
2.49E-02
SN-126
66. 31
1.21B-01
SH-126
79.2%
3.64E-01
SH-126
83. OZ
1.86E+03
AM-243
35,71
1/78E+Q3
TO-239
36. LZ
100.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
9.341-06
SR -90
62. OZ
3.84E-04
SR -90
48. 1Z
9.90E-04
TC -99
42. 8Z
5.6ZE-03
TO -99
50.71
5.49E-02
SN-126
68. ?Z
2.21E-01
SN-126
80. 5Z
3.93E+01
AH-243
35. 2Z
1.3BE+03
PU-239
36.11
200.00
0.0
HOHE
O.OZ
0.0
NONE
O.OZ
0.0
KOBE
O.OZ
6.09B-06
SR -90
48.11
3.54E-04
TC -99
42.8*
3.20E-03
1C -99
52. 2Z
1.16E-02
fG -99
51.0Z
1.06E-01
SN-126
71.9Z
3.82E-01
SN-126
84. 3Z
6.19E»01
PU-239
36. OZ
500.00
0.0
HONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
9.57E-04
1C -99
52. 2Z
5.52B-03
TC -99
52. 7Z
1.71E-02
TC -99
53. 8Z
1.83E-01
SN-126
79. 4Z
2.20E-01
SH-126
88.61
750.00
0.0
HONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
mm
O.OZ
0.0
HONE
0.01
Z.64E-04
K5 -99
52.21
3.471-03
TC -99
52. n
1.2SB-02
TC -99
53. 8Z
8.91E-02
SN-126
65. SZ
1.94E-01
SN-126
89. 3Z
IODO.OO
0.0
NONE
O.OZ
0.0
NOME
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
9.31E-06
TC -99
52.2%
2. 171-03
TC -99
52. 7%
1.01E-02
1C -99
53. 8Z
2.92E-02
TC -99
50. 6Z
1.70E-01
SN-126
89.2%
1500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
6.36E-04
TC -99
52. 7Z
6.5BE-03
TC -99
53. 8Z
2.09E-02
TC -99
56.4*
1.03E-01
SN-126
85. OX
2009.00
0.0
HOHE
O.OZ
0.0
NONE
O.OZ
0,0
HONE
0.0!
0.0
HONE
D. 01
0.0
HOHE
O.OZ
0.0
HONE
0.01
2.17E-05
TC -99
52. 71
4.30E-03
TC -9.9
53. 8Z
1.76E-02
TC -99
56. 4%
2.061-02
TC -r99
39. 9Z
4000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
5.26E-05
TC -99
53. 8Z
1.03E-02
TC -99
56.4Z
1.10E-02
TC -99
59 .4%
-------
Table 6.16
Area (ha*) of the Aquifer Contaminated
Above the Specified Dose Rate Levels
Because of Drilling 1000 Years after Sealing
No solubility limits
Event description
Direct hit
on waste
Brine pocket
to surface
Granite tank
to aquifer
Brine pocket
to aquifer
Length of time
after event (yr)
0-500
1000
2000
5000
10000
10
20
50
100
200
500
1000-10000
0-500
1000
2000
5000
10000
0-500
1000
2000
5000
10000
Dose Rate Levels (rem/yr)
0.5
0
0.33
0.31
2,37
7.35
0.65
0.64
0.62
0.59
0.53
0.34
0
0
0.36
0.34
2.74
8.78
0
0.35
0.32
2.53
7.96
5
0
0.28
0.24
1.63
4.35
0
0
0
0
0
0
0
0
0.30
0.29
2.13
6.47
0
0.29
0.26
1.85
5.30
50
0
0.20
0.15
0.04
0
0
0
0
0
0
0
0
0
0.24
0.22
1.25
2.59
0
0.22
0.18
0.67
0
500
0
0.07
0
0
0
0
0
0
0
0
0
0
0
0.15
0.11
0
0
0
0.12
0
0
0
*1 hectare (ha) = 10^ square meters
NOTE: Shaft seal release are very similar to direct hit drilling.
141
-------
the nuclide inventory available to groundwater, we would expect that
the dose rates at higher leach rates would fall off more rapidly as the
dose times increase.
6.3.1 Release to the aquifer due to drilling
Direct hit on waste
Tables 6.17, 6.18 and 6.19 show the annual dose rates from
drinking aquifer water after a direct hit on waste with leach rates
-2 -3 -5 -1
of 10 ,10 and 10 yr , respectively. Together with Table 5.7,
they show the effect of a changing leach rate upon the results of this
event. For the first 100 years after the event, the dose rate varies
linearly with the leach rate. However, as dose times increase and
waste inventory is depleted by leaching, the dose rates deviate from
-2
linearity. For example, after 500 years, with a leach rate of 10 ,
over 99% of the available waste has been removed (ignoring radioactive
decay). This is reflected in the sharp drop in the annual dose rates
2
after 1000 years for a leach rate of 10 , and after 5000 years for a
_o
leach rate of 10 . The rapid depletion of the inventory produces a
very small band of contamination for isotopes with retardation factors
of 100. All the americium, for instance, that is leached in 500 years
is in a band only as wide as the distance it travels in 500 years,
10.5 meters. The corresponding bands for nuclides with retardation
factors of 10 and 1 are 105 meters and 1050 meters wide. Since Am-241
and -243 are dominant and have retardation factors of 100, their con-
tribution to the dose rate is limited to time and distance such that
distance equals approximately 0.021 times dose time.
Cs-135 and Sn-126 are dominant for dose times less than
1000 years. At 1000 years, americium appears in all cases because
nuclide movement in the aquifer does not depend on leach rate. The
dose rates in Table 6.17 reach a high of 39,000 rem/yr at 1000 years
and 20 meters, and then fall off very quickly. The maximum annual dose
rate would actually be calculated at 21 meters due to the high leach
rate. The 5000-year dose time shows a significant dose at 100 meters,
142
-------
Table 6.1?
TIHE (yr)
l.OOE+01
2.00E+01
5.00E+01
l.OOB+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
1.001+04
Dose Equivalent Rates (rem/yr) from Drinking Grounduater Contaminated by Radionuclidea
Released by Borehole Drilling
1000 Years After Repository Sealing
Drill Hit* Waste
Leach Rate " 10~2 per year
DISTANCE (meter*)
20,00
1.95E-01
CS-135
58.7%
1.75E-01
CS-135
58.7*
1.30E-01
CS-135
58.81
2.21E+00
SN-126
96.4%
••saiE-oi
' SN-126
96.4%
4.03E-02
SN-126
96.5%
3.90E+04
AM-241
93.11
5.181-01
AM-241
70.0%
2.20E-14
AH-243
36. OX
2.96E-36
TO-239
36.82
50.00
0.0
HONE
O.OZ
0.0
HONE
0.01
9.511-02
CS-135
58.81
5.75E-02
CS-135
58. 9Z
2.11B-02
CS-135
59.2%
1.04E-01
SN-126
99. OS
6.99E-Q4
SH-126
98. 5Z
3.17E-08
SN-126
98. OZ
2.22E-08
AM-243
36.0Z
3.00E-30
PO-239
36.8Z
100.00
0.0
NONE
O.OZ
0.0
HONE
O.OZ
8.531-02
CS-135
58.81
5.16E-02
CS-135
58. 9Z
1.89E-02
CS-135
59. 2%
7.95E-01
SN-126
99, 9Z
5.27E-03
SN-126
99. 8%
2.381-0?
SH-126
99. 8*
1.30E+02
AH-243
95. 6Z
4.64E-20
PU-239
36.8%
200.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
MORE
O.OZ
5.888-02
GS-135
58.9Z
2.15E-02
CS-135
59. 2Z
1.06E-03
CS-135
60, OZ
4.36B-01
SN-126
100.0Z
1.96E-05
SH-126
100. OZ
1.80E-18
SN-126
100.0Z
5.16E+00
AM-243
99.8%
500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
0,0%
2.79E-03
CS-135
60.1%
1.95E-05
CS-135
58. OZ
1.74E-09
1C -99
54.3%
1.82E-12
SN-126
100.0Z
3.39E-34
SN-126
100.0Z
750.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
BONE
O.OZ
7.48E-03
CS-135
60. 1Z
5.02E-05
CS-135
60.4%
4.68E-09
fC -99
54. 3Z
2.20E-07
SN-126
100.0%
4.10E-29
SN-126
100. OZ
1000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NOME
O.OZ
0.0
HOHE
O.OZ
2.13E-OZ
CS-135
60. 1Z
1.41E-04
CS-135
61.1%
1.33E-08
TC -99
54. 3Z
2.82E-02
SN-126
100.0%
5.25E-24
SN-126
100.0%
1500.00
0.0
NONE
0.01
0.0
NONE
Q.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
O.OZ
1.24E-03
CS-135
61.5%
I. 181-07
TC -99
54. 3%
1.04E-20
XC -99
56.8Z
9.39E-14
SH-126
100,0%
2000.00
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HOHE
O.OZ
0,0
NONE
0.0%
0.0
HONE
O.OZ
1.16E-02
CS-135
61.5%
1.03B-06
TC -99
51.1%
9.76E-20
TC -99
56.8%
1.78E-03
SN-126
100.0%
4000.00
0.0
HOHE
O.OZ
0,0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
O.OZ
4.88E-03
CS-135
64.2Z
9.441-16
TC -99
56.81
1.71E-37
TC -99
59.6%
-------
Table 6.18
Dote Equivalent Kate* (rea/ff) froa Drinking Grounds -\ter Contaminated by Rsdionuclidea
Released by Borehole Drilling
1000 Year* fitter Repository Sealing
Drill Bit* Waste
Le^ch Kite «• 10"-* ()*r year
DISTANCE (meter*)
TIMS (yr)
l.OOE+01
2.00E+01
5.001+01
i.OOE+02
2.00E+02
5.00E+02
1.00B+D3
2.00E+03
5.00E+03
1.00E+04
20.00
1.96E-02
CS-135
58.61
1.94E-02
CS-135
58,7%
1.8BE-02
CS-135
58. 82
2.40E-01
SH-126
92.6%
2.17E-01
SN-126
92.61
1.60E-01
SH-126
92. 7Z
5.98E+03
AM-241
93. n
5.89E402
&M-241
76. 6X
5.511*00
AM-243
95. OS
4.76E-02
Att-243
47. IZ
SO.OO
0.0
NOHE
O.OZ
0.0
NONE
0.0%
1.2QS-02
CS-135
58.81
1. 14E-02
CS-135
58.9Z
1.03E-02
CS-135
59.2%
1. 16E-01
SN-125
93, 5Z
6.99E-02
SH-126
93. 6%
2.551-02
SS-126
93.8%
1.45B+OL
AM-243
95. 5%
7 . 62E-02
AM-243
77, 6%
100,00
0.0
NONE
o.oz
0.0
NONE
O.OZ
8. 72B-03
C8-135
58, at
8.271-03
CS-135
58. 9%
7.45E-03
CS-135
59.2%
1.03E-01
5S--126
94. 7Z
6.20E-02
SH-126
94.8%
2.26E-02
SH-126
95.01
l.WE+02
AM-243
95. 6X
4.63E-01
AM-243
97.7%
200.00
0.0
HONE
0.0%
0.0
NONE
O.OZ
0.0
NOME
O.OX
6.14E-03
CS-135
58.9%
5.53E-03
GS-135
59.2Z .
4.04E-03
CS-135
60. U
6.92E-02
SH-126
96.5%
2.53E-02
SH-126
96. 7X
1.23E-03
SN-126
96.9Z
3.74E+01
AM-243
100. OJ
500.00
0.0
HONE
O.OZ
0.0
NONE.
O.OZ
0.0
HONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
0,0%
2.94E-03
CS-135
60.1%
1. 74S-03
CS-135
61.4Z
6.15E-04
CS-135
64. 1%
3.17E-03
SH-126
99. n
2.09E-05
SK-126
98.1%
750.00
0.0
NONE
0.0%
0.0
HONE
O.OZ
0.0
HONE
O.OZ
0.0
HOSE
0.0%
0.0
HONE
0.0%
2.71E-03
CS-135
60.1%
U60E-03
CS-135
61.5%
5.65B-04
CS-135
64. U
8.47E-03
SH-126
99.7%
5.53E-05
SN-126
99.3%
1000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONI
O.OZ
0.0
HONE
0.0%
2.64E-03
CS-135
60.1%
1.57B-03
CS-135
61.5%
5.52E-04
CS-135
64.2%
2.41E-02
SH-126
99.9%
1.57E-04
SH-126
99. 8S
1500.00
0.0
NONE
O.OJ
0.0
NONE
O.OZ
0.0
mm
O.OZ
0.0
HONE
O.OZ
0.0
NONE
0.02
0,0
NONE
O.OZ
1.62E-03
CS-135
61.5%
5.71B-04
CS-135
64.2%
2.58E-05
CS-135
70.6%
1.38E-03
SN-126
100. OS
2000.00
0.0
NONE
O.OZ
0.0
NOME
O.OZ
0.0
HONE
O.OZ
0.0
HOW
O.OZ
0.0
NONE
0.0%
0.0
NONE
O.OZ
1.78E-03
CS-135
61.51
6.28S-04
CS-13S
64.2%
2.836-05
CS-135
70.81
1.29E-02
SH-126
100. OS
4000.00
0.0
HONE
O.OZ
0.0
HOME
0.0%
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
O.OZ
1.15E-03
CS-135
64.2%
5.14E-05
CS-135
71.«
5.49E-07
CS-135
45.01
-------
Table 6.19
TIME(yr)
l.OOE+01
2,001+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
Dose Equivalent Rates (rea/yr) frera Drinking Grounduater Contaminated fcy Radionuciidea
Released by Borehole Drilling
1000 Years After Repository Sealing
Drill Hits Haste
Leach Rate » 10~5 per year
DISTANCE (meters)
20.00
2.03E-04
CS-135
56. 7Z
2.02E-04
CS-135
56. 8Z
2.02E-Q4
CS-135
ss. 9z
2.43E-03
SH-126
91. 7Z
2.43E-03
SN-126
91. 8Z
2.4 IE -03
SN-126
91.9%
6.28E+01
AM-241
93. iz
1.67B+01
AH-241
76.4%
3.04E+00
AM-243
94. 5Z
1.77E+00
AM-243
98.21
50.00
0.0
HOME
O.OZ
0.0
NOME
O.OZ
1.28E-04
CS-135
56. 9Z
1. 27E-04
CS-135
57.0%
1.26E-04
CS-135
S7.3Z
1.53E-03
SH-126
91. 9Z
1.51E-03
SH-126
92.0Z
1.48E-03
SH-126
92. 3Z
1.95E*00
AM-243
94. SZ
1. 13E+00
AM-243
98. 4Z
100.00
0.0
mm
O.OJ
0.0
NONE
o.oz
9.04E-05
CS-135
56. 8Z
9.01E-05
C8-135
57. OZ
8.95E-05
CS-135
57.3Z
1.08B-03
SN-126
91.91
1.07E-03
SN-126
92. 1Z
1.05E-03
SN-126
92. 3Z
1.42E+00
AK-243
94. 3Z
8.20E-01
AM-243
98. 61
200.00
0.0
NONE
O.OZ
0,0
NONE
O.OZ
0.0
HONE
O.OZ
6.37E-05
CS-135
57. OZ
6.33E-05
CS-135
57. 3*
6.21E-05
CS-135
58.3JS
7.61E-04
SN-126
92. 1Z
7.46K-04
SN-126
92. 4Z
7.04E-04
SH-126
93. OZ
6.08E-01
AM-243
98. 5Z
500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
HOWE
O.OZ
0.0
NONE
O.OZ
3.941-05
CS-135
58.21
3.82E-05
08-135
59. 7Z
3.61E-05
CS-135
62. 5Z
4.51E-04
EN- 126
93. 1Z
4.12E-04
SN-126
93. 7Z
750.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0,0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
3.22E-05
CS-135
ss. n
3.12E-05
CS-135
59. 7Z
2.95E-05
CS-135
62. 5Z
3.73E-04
SN-126
93. 1Z
3.40E-04
SH-126
93. 7Z
1000.00
0.0
NOHE
O.OZ
0.0
NONE
O.OZ
0,0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NOME
O.OZ
2.80E-05
CS-135
58. 1Z
2.71E-05
CS-135
59. 6%
2.561-05
CS-135
62. 5Z
3.26E-04
SN-126
93. 2%
2.98E-04
SH-126
93. 8Z
1500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
2.22E-05
CS-135
59. 5Z
2.10E-05
CS-135
62. 4Z
1.81E-05
CS-135
70. OZ
2.49E-04
SN-126
93. 9Z
2000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NOHE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
1.93E-05
CS-135
59 .4Z
1.82E-05
CS-135
62 -4Z
1.57E-05
CS-135
70. OZ
2.20E-04
SN-126
94. OZ
4000.00
0.0
N0«
O.OZ
0.0
NONE
O.OZ
0.0
NOHE
O.OZ
0.0
NOHE
O.OZ
0.0
HONE
O.OZ
0.0
NOHE
O.OZ
0.0
HONE
O.OZ
1.31E-05
CS-135
62.0Z
1.13E-05
CS-135
69. 9Z
9.37E-06
CS-135
79. 7Z
-------
Table 6.20
Area (ha*) of the Aquifer Contaminated
Above the Specified Dose Rate Levels
Following a Direct Drilling Hit on Waste
1000 Years after Sealing
Variable leach rates
Leach Rate Length of time Dose Rate Levels (rem/yr)
(per year) after event (yr)
ID'2 0-50
100
200
500
1000
2000
5000
10000
lO"3 0-500
1000
2000
5000
10000
10~4 0-500
1000
2000
5000
10000
10~5 0-500
1000
2000
5000
10000
0.5
0
0.15
0.09
0.49
0.42
0.02
1.73
4.23
0
0.38
0.33
2.41
5.76
0
0.33
0.30
2.10
6.11
0
0.27
0.23
1.24
0.07
5
0
0
0
0
0.37
0
1.33
0.48
0
0.33
0.27
1.62
3.93
0
0=27
0.23
1.20
1.26
0
0.20
0.14
0
0
50
0
0
0
0
0.32
0
0.72
0
0
0.27
0.20
0.65
0
0
0.20
0.13
0
0
0
0.06
0
0
0
500
0
0
0
0
0.26
0
0
0
0
0.20
0.05
0
0
0
0.06
0
0
0
0
0
0
0
0
5000
0
0
0
0
0.18
0
0
0
0
0.05
0
0
0
0
0
0
0
0
0
0
0
0
0
*1 hectare (ha) = 10^ square meters
146
-------
which is within the 105-meter contaminated band. The low solubility of
Plutonium prevents it from leaching quickly and, further, causes it to
spread out over a larger area.
Table 6.18 is for a leach rate of 10" yr~ . The contami-
nation band in this case is about 105 meters for isotopes with a
retardation factor of 100. The peak dose rate, about 6000 rem/yr (93%
from Am-241) occurs at 20 meters and 1000 years. After 5000 years,
amerlcium doses increase with distance away from the borehole (up to
200m) because the nuclides at the larger distances were released
earlier, before the waste was depleted by leaching.
Table 6.19 does not show any increasing annual dose rates with
larger distances because the leach rate of 10 yr" is so low.
The maximum dose rate is 63 rem/yr, 93.1% from Am-241. Cs-135 and
Sn-126 dominate all distances until 1000 years when Am-241 reaches the
20-meter distance. Then until 10,000 years Cs-135 and Sn-126 are the
prominent nuclides at the large distances while Am-241 and Am-243
dominate up to 200 m.
The smaller leach rates produce lower doses, but the area is
contaminated longer. Dose rates from the large leach rates peak high
and early, then decrease rapidly. Table 6.20 shows areas contaminated
over 0.5 rem/yr. The portion of the table for a leach rate of
2 1
10 yr probably underestimates the actual area contaminated,
because the very small contamination band may be missed between the
points selected for numerical integration.
Granite tank
Tables 6.21 through 6.23 give the annual dose rates resulting from
drilling into the water in the granite tank 1000 years after sealing,
assuming leach rates of 10~2, 10"3, and 10~5 yr . Table 5.17
gives the annual dose rates for this event with a leach rate of
10 yr . The dose rates at 20 meters and 1000 years range from
4900 rem/yr at the highest leach rate to 200 rem/yr at the lowest. The
amount of a nuclide leached into the tank during the 500 years between
147
-------
canister failure and the 1000-year drilling event is important in
controlling the dose rates, particularly at the early dose times and is
strongly affected by the leach rate. When the leach rate is
10" yr" , only 0.005 of the nuclide has leached into the tank in
-4
the 500 years between canister failure and drilling; at 10 per
year, 0.05; at 10"3» 0.39; and, at TO"2, over 0.99. At the lowest
leach rate the dose rates increase proportionally to the leach rate
(factor of 10 between 10 and 10~ ), but then somewhat higher
(factor of about 16 between 10 and 10 , and factor of about 25
-3 -2
between 10 and 10 ). For higher leach rates, the dose rates at
later times fall sharply, as the nuclide inventory is depleted. Even
at the base case leach rate of 10 per year, 63% of a nuclide has
been removed in 10,000 years.
Table 6.24 shows the areas contaminated at the three leach rates.
Less severely contaminated areas (0.5-5 rem/yr) are not greatly
affected by leach rate. Very heavily contaminated areas are smaller
and less persistent with the lower leach rates. Since the leach rate
is not a function of the nuclide itself but of the waste matrix, the
same nuclides will dominate the same locations in the aquifers for all
leach rates. Cs-135 dominates the first 50 years. At 100 years,
Sn-126 has moved to a point where it delivers a dose. Farther
downstream is the Cs-135. At 1000 years, Am-241 dominates the dose at
20 meters, followed by Sn-126 and Cs-135. As the Am-241 decays, Am-243
gains in importance. The latter years feature Am-243 and Sn-126 as the
important nuclides. As the annual dose rates drop with the decreasing
leach rates, the corresponding contaminated areas also decrease.
Brine pocket
This scenario is the same as described in section 5.1.2 with
exception of the leach rates examined. Table 6.25 presents the results
-------
Table 6.21
10
TIME (yr)
l.OOE+01
2.00E+01
5.00E+01
l.OOE+02
2.001+02
5.00E+02
l.QOE+03
2.00E+03
5.00E+03
I.OOE-KJ4
Dose Equivalent Rates (rera/yr) from Drinking Groundwater Contaminated by Radionuclides
Released by Borehole Drilling in GRANITE
1000 Years after Repository Sealing
Drill Bits Repository Hater
Leach Rate « 10~2 per year
DISTANCE (meters)
zo.oo
1.59E-02
OS- 135
58.6%
1.58E-02
CS-135
58.7*
1.53E-02
CS-135
58.8X
1.96E-C1
SH-126
92.61
1.77E-01
SH-126
92.6%
1.31E-01
SN-126
92. 7Z
4.88E+03
AM-241
93. IX
4.81E+02
AM-241
76.61
4.45E+00
AM-243
94. 81
4.00E-02
AM-243
45.21
50.00
0.0
HONE
O.QZ
0.0
NOME
O.OZ
9.82E-03
CS-135
58.81
9.31E-03
CS-135
58.9%
8.37B-03
CS-135
59.21
9.45E-02
SH-126
93.51
5.70E-02
SH-126
93.62
2.07E-02
SH-126
93.82
1.18E+01
AM-243
95.41
6.54E-02
AM-243
73. 9%
100.00
0.0
NONE
o.oz
0.0
NONE
O.OZ
7. 10E-03
CS-135
58.82
6.75E-03
CS-135
58.9Z
6.0BE-03
CS-135
59. 2%
8.36E-02
SH-126
94. 7Z
5.06E-02
SH-126
94. 8Z
1.S4E-02
SH-126
94. 9Z
9.00E+01
AK-243
95. 6Z
3.75E-01
AM-243
97.1%
200.00
0.0
-NONE
0.0%
0.0
NCHE
O.OZ
0.0
NONE
O.OZ
5.00E-03
CS-135
58.9Z
4.51E-03
CS-135
59.2%
3.29E-03
CS-135
60.0%
5.65E-02
SH-126
96.5%
2.06E-02
SN-126
96.61
9.931-04
SH-126
96.82
3.05E+01
AM-243
100.0%
500.00
O.D
NONE
O.OZ
0.0
HONE
0.0%
0.0
NOHE
O.OZ
0.0
NONE
0.02
0.0
HONE
0.0%
2.40E-03
CS-135
60.12
1.42E-03
CS-135
61.42
5.00E-04
CS-135
64.12
2.581-03
SN-126
99.12
1.71E-05
SN-126
98.12
750.00
0.0
NONE
0.02
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NOHE
O.OZ
0.0
NONE
O.OZ
2.21E-03
CS-135
60. 12
1.31E-03
CS-135
61.4Z
4.60E-04
CS-135
64. 1Z
6.92E-03
SH-126
99.7%
4.47E-05
SN-126
99.3%
1000.00
0.0
HONE
0,02
0.0
NOHE
O.OZ
0.0
NONE
O.OZ
0.0
NOHE
O.OZ
0.0
NOHE
O.OZ
2.15E-03
CS-135
60. 1Z
1.28E-03
CS-135
61.42
4.49E-04
CS- 135
64. 1Z
1.96E-02
SH-126
99. 9Z
1.26E-04
SN-126
99. 8%
1500.00
0.0
HONE
O.OZ
0.0
NOHE
0.02
0.0
HONE
0.02
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
HONE
0.02
1.32E-03
CS-135
61.52
4.66B-04
CS-135
64.22
2.10E-05
CS-135
70.32
1.13E-03
SH-126
100. 0%
2000.00
0.0
HONE
O.OZ
0.0
NOHE
O.OZ
0.0
NOHE
0.02
0.0
NONE
0.0%
0.0
NONE
0.02
0.0
NOHE
O.OZ
1.45E-03
CS-135
61. 5%
5.121-04
CS-135
64.22
2.29E-05
CS-135
70.62
1.05E-02
SN-126
100.02
4000.00
0.0
NONE
O.OZ
0.0
HOHE
0.02
0.0
NOHE
O.OZ
0.0
NOHE
0.02
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
9.371-04
CS-135
64.22
4.20E-05
CS-135
71.32
4.92E-07
1C- 99
50.22
-------
Table 6.22
en
o
TIIC (yrj
l.OOE+01
2.00E+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
1,DOE+04
Dose Equivalent Rates (ren/yr) (ran Drinking Gtoundvater Contaminated by Radionuctides
Released by Borehole Drilling la GRANITE
1000 Years After Repository Seating
Drill Hits Repository Water
Leach Rate " 10~^ per year
DISTANCE (meters)
20.00
3.93B-04
CS-135
57.71
3.96E-04
CS-135
57, 73
3.95E-04
CS-135
57. 8Z
4.83E-03
SB- 126
91.81
4.82E-03
SH-126
91,91
4.79E-D3
SH-126
92.01
1.25E+02
AM-241
93.1%
3.31E+01
AM-241
76. 5%
5.96E+00
AM-243
95.02
3.45E+00
AM-243
99.0%
50.00
0.0
NONE
0.02
0.0
HONE
0.02
2.50E-04
CS-135
57.8%
2.49E-04
CS-135
58.02
2.47E-04
CS-135
58.31
3.04E-03
SH-126
92.0%
3.00E-03
SH-126
92.11
2.93E-03
SN-126
92. 3Z
3.85E+00
AH-243
95.02
2.24E+00
AH-243
99. IX
100.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
1.77E-04
CS-13S
57.81
1.76E-04
CS-135
58. OZ
1.75E-04
CS-135
58. 3Z
2.15E-03
SH-126
92. OZ
2.13S-03
SH-126
92.2%
2.08E-03
SH-126
92.4Z
2.80E+00
AM-243
94.92
1.60E+00
AM-243
99. 2Z
200.00
0.0
NONE
O.OZ
0.0
HONE
0.02
0.0
NONE
0.02
1.25E-04
CS-135
57.92
1.24E-04
CS-135
58.22
1.22E-04
CS-135
59. IZ
1.51E-03
SH-126
92. 2Z
1.48E-03
SH-126
92 .4Z
1.38E-03
SH-126
93.02
1.201+00
AM-243
99.22
500.00
0.0
NOME
0.02
0.0
HONE
O.OZ
0.0
NONE
0.02
0.0
HONE
0.02
0.0
NONE
0.02
7.71E-05
CS-135
59.12
7.48E-05
CS-135
60. 6%
7.05E-05
CS-135
63.42
8.95S-04
SH-126
93.22
8.21E-04
SN-126
93.82
750.00
0.0
NOME
O.OZ
0.0
NONE
0.02
0.0
NONE
0.02
0.0
HONE
0.02
0.0
NONE
0.02
6.30E-05
CS-135
59.12
6.12E-05
CS-135
60,61
5.77E-05
CS-135
63.42
7.41E-04
SH-126
93.32
6.70E-04
SN-126
93.82
1000,00
0.0
NONE
0.02
0.0
NONE
0.02
0.0
HONE
0.02
0.0
HONE
0.02
0.0
NONE
0.02
5.46E-05
CS-135
59.02
5.31E-05
CS-135
60.52
5.01E-05
CS-135
63.32
6.48E-04
SN-126
93.32
5.85E-04
SH-126
93. 8Z
1500.00
0.0
HONE
O.OZ
0.0
HONE
O.OZ
0.0
HONE
0.02
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NOHE
0.02
4.35E-Q5
CE-135
60.52
A.I IB-OS
CS-135
63.32
3.53E-05
CS-135
70.92
4.96E-04
SN-126
94.12
2000.00
0.0
NONE
O.OZ
0,0
HONE
0.02
0.0
HONE
0.0%
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
O.OZ
3.78E-05
CS-135
60.42
3.57E-05
CS-135
63.32
3.06E-05
CS-135
70. 9Z
4.37E-04
SH-126
94.21
4000.00
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
O.OZ
0.0
NOHE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
2.55E-05
CS-135
63.12
2.20E-05
CS-135
70.9%
1.83B-05
CS-135
80.82
-------
table 6,23
TIME (yr)
l.OOE+01
2.00E+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
Dose Equivalent Rates (rem/yr) from Drinking Groundwater Contaminated by Radionuctides
Released by Borehole Drilling in GRANITE
1000 Years After Repository Sealing
Drill Hits Repository Water
Leach Rate » 10"' per year
DISTANCE (meters)
20.00
5.55E-04
CS-135
58.31
5.62E-04
CS-135
58.3%
5.83E-04
CS-135
58. 5%
6.94E-Q3
SN-126
91.11
7.78E-03
SN-126
91. 3Z
9.73E-03
SN-126
91. 7%
1.88E+02
AH-241
93. 1Z
8.50E+01
AM-241
76.631
1.66E+01
AH-243
95.5%
4.39E+00
AH-243
99.9%
50.00
0.0
NONE
0.0%
0.0
HONE
O.OZ
3.62E-04
OS-13S
.58.51
3.83K-04
CS-135
58. 6%
4.21E-04
CS-135
59.01
5.65E-03
SH-126
91.11
7.15E-03
SH-126
91.82
8.45E-03
SH-126
92. 4Z
1.14E+Q1
AB-243
95. 5%
3.7QE+OQ
A»-243
99.9%
100.00
0.0
NONE
0.0%
0.0
NONE
0.0%
2.48E-04
CS-135
58.4%
2.64B-04
CS-135
58.6%
2.91E-04
CS-135
58.9%
3.24E-03
SN-126
89. 1 X
4. 641-03
SS-126
91. U
5.84E-03
SH-1Z6
92.2%
4.94E+OQ
AM-243
97.4%
3.91E+00
AW-243
99.9%
200.00
0.0
HONE
O.OZ
0.0
HONE
0.0%
0.0
KOHE
O.OZ
1.76E-04
CS-135
58.6%
1.97E-04
CS-135
58.9%
2.43E-04
CS-135
59.9%
2.39E-03
SN-126
87. 9*
3.84E-03
SN-126
91.7%
3.86E-03
SN-126
93.7%
2.51E-MW
AH-243
99.8%
500.00
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
HONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
1.40E-Q4
CS-135
59.8%
1.75E-04
CS-135
61. 3Z
2.01E-04
CS-135
64,1%
2.64E-03
SH-126
94.1%
1.33E-03
SN-126
95. 9%
750.00
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
O.OZ
1.04E-04
CS-135
59,8%
1.37E-04
CS-135
61. 3S
1.62E-04
CS-135
64.1%
2.03E-03
SN-126
93. 6%
1.34E-03
SN-126
96.5%
1000.00
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
HONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
O.OZ
7.90E-05
CS-135
59.7%
1.13E-04
CS-135
61.3%
1.39E-04
CS-135
64,1%
1.21S-03
SN-126
90.6%
1.39E-03
SN-126
97. OZ
1500.00
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
O.OZ
8.06E-05
CS-135
61.2%
1.09E-04
CS-135
64.1%
9.55E-05
CS-135
71.8%
1.41E-03
SN-126
97.5%
2000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
u.o
NONE
0.0%
0.0
NONE
0.0%
0.0
HONE
0.0%
5.62E-05
CS-135
61. 1Z
9.06E-05
CS-135
64. 1Z
8.48E-05
CS-135
71.8%
9.00E-04
SN-126
96.4%
4000.00
0.0
NONE
O.OZ
0.0
NONE
o.ot
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
0.0%
4.01E-05
CS-135
63.9%
6.43E-05
CS-135
71. 8Z
2.77E-05
CS-135
81.9%
-------
Table 6.24
Area (ha*) of the Aquifer Contaminated
Above the Specified Dose Rate Levels
Following Drilling into the Granite Tank
1000 Years after Sealing
Variable leach rate
Leach Rate Length of time Dose Rate Levels ,(rem/yr)
(per year) after event (yr)_
10~2 0-50
100
200
500
1000
2000
5000
10000
10"3 0-50
100
200
500
1000
2000
5000
10000
10*"5 0-500
1000
2000
5000
10000
0.5
0
0.12
0.12
0.57
0.51
0.38
3.00
9.42
0
0.04
0.05
0.06
0,40
0.37
2.91
9.15
0
0.30
0.28
1.83
5.15
5
0
0
0
0
0.37
0.33
2.46
7.30
0
0
0
0
0.35
0.32
2.34
6.96
0
0.24
0.21
0.39
0
50
0
0
0
0
0.32
0.27
1.75
3.98
0
0
0
> 0
0.30
0.26
1.58
3.42
0
0.14
0.09
0
0
500
0
0
0
0
0.25
0.19
0.38
0
0
0
0
0
0.23
0.18
0
0
0
0
0
0
0
3000
0
0
0
0
0.17
0.04
0
0
0
0
0
0
0.13
0
0
0
0
0
0
0
0
*1 hectare (ha) = 10* square meters
152
-------
Table 6.25
TIME lyr)
l.OOE+01
2.0QE+01
5.00E+Q1
l.OOE+02
2.0QEMJ2
5.00E+02
i.OOE+03
2.00E+Q3
5.00S+03
l.OOE+04
Dose Equivalent Rate* (rem/yr) from Drinking Groundu«ter Contaminated by Radionucliden
Released by Borehole Drilling in BEDDED SALT
1000 Year* After Repository Sealing
Drill Hits Repository Water
Leach R«t« » 10"* per year
DISTANCE (meters)
20.00
5.46E-05
OS- 135
51.5%
5.03E-05
CS-135
50.91
3.89E-OS
CS-135
48. 8Z
5.53E-04
SN-126
95.32
2.Q7E-04
SN-126
93. SI
1.041-05
SN-126
92.81
9.72E+00
AM-241
92.62
1.61E-04
AM-241
55.8%
S.39E-18
AH-243
36.01
6.80E-40
PO-239
39. 2Z
50.00
0.0
NOME
O.OZ
0.0
HOME
0.0%
2.78S-05
CS-135
49.92
1.84E-05
OS- 135
45.72
9.22E-06
1C -99
43. 5%
2.60E-05
SN-126
97.92
1.74E-07
SN-126
97.92
7.82E-12
SN-126
97.92
5.50E-12
AM-243
36.0%
7.46E-34
PU-239
36.82
100.00
0.0
NONE
0.0%
0.0
HONE
0.0%
2.41E-05
CS-135
51.52
1.57E-05
CS-135
47. 9Z
7.54E-06
TC -99
37.9%
1.95E-04
SH-126
99.82
1.31E-06
SN-126
99.82
5.88E-11
SN-126
99.82
4.97E-02
AM-243
61.7%
1. 14E-23
PU-239
36.8%
200.00
0,0
HONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.02
1.67E-05
CS-135
51.52
7.38B-06
CS-135
42.8%
5.53E-07
TC -99
52.7%
1.081-04
SN-126
100.02
4.87E-09
SH-126
100.0%
4.42E-22
SN-126
100.0%
3.90E-03
PO-239
36.8%
500.00
0.0
NONE
O.OX
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
O.OZ
0.0
NONE
0.0%
1.46E-06
TC -99
52.72
9.72S-09
TC -99
53. 3Z
4.30E-13
TC -99
54.32
4.51E-16
SN-126
100.0%
8.44E-38
SN-126
100.0%
750.00
0.0
NONE
0.0%
0.0
NONE
0.02
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.0%
2.90E-06
CS-135
38.42
2.61E-08
TC -99
53. 3Z
1. 16E-12
TC -99
54. 3%
5.46E-11
SN-126
100.0%
1.01E-32
SN-126
100.02
1000.00
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.02
0.0
NONE
O.OZ
0.0
NONE
0.02
6.22E-06
CS-135
51.0%
7.44E-08
TC -99
53.3%
3.29E-12
TC -99
54.32
6.98E-06
SN-126
100.0%
1.29E-27
SN-126
100.0%
1500.00
0,0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
O.OZ
6.57E-07
TC -99
53.32
2.92E-11
1C -99
54.32
I. 561-24
TC -99
56.8%
2.34E-17
SH-126
100.0%
2000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0,0
NONE
O.OZ
0.0
NONE
0.02
0.0
NONE
O.OZ
3.531-06
CS-135
50.02
2.73E-10
TC -99
54.3%
2.39E-23
TC -99
56.8%
4.41E-07
SN-126
100.0%
4000.00
0.0
NONE
0.0%
0.0
NONE
0.02
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
HONE
0.0%
0.0
NONE
O.OZ
1.66E-06
CS-135
46.6%
2.34E-19
TC -99
56.8%
4.21E-41
TC -99
59.6%
-------
table 6.26
tn
TIME (yr)
l.OOE+01
Z.OOE+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
Dose Equivalent Rates Crem/yr) from Drinking Groundwater Contaminated by Radiomiclide»
Released by Borehole Drilling in BEDDED SALT
1000 Vears After Repnnitory Sealing
Drill Hita Repository Water
Leach Rate " 10"^ per year
DISTANCE (meters)
20.00
1.59E-02
OS- 135
58.62
1.58E-02
CS-135
58.72
1.5.-E-02
CS-135
5B.8Z
1.96E-01
SN-126
92.62
1.77E-01
SN-126
92.61
1.311-01
SN-126
92.71
4.88E+03
AM-241
93. 11
4.81E+02
AM-241
76.62
4.45E+00
AM-243
94. 8 X
4.00E-02
AM-243
45. 2*
50.00
0.0
HONE
O.OZ
0.0
HONE
O.OZ
9.82B-03
CS-135
53.81
9.31E-03
CS-135
58.91
8.37E-03
CS-135
59. 21
9.45E-02
SN-126
93. 5Z
5.70E-02
SH-126
93.61
2.07E-02
SH-126
93. 8Z
1.18E+01
AM-243
95 .4*
6.54E-02
AM-243
73.9%
100.00
0.0
HOKB
o.ox
0.0
NONE
O.OZ
7 . 10E-03
CS-135
58.8?
6.75E-03
CS-135
58.91
6.081-03
CS-135
59.21
8.36E-02
SH-126
94. 7Z
5.06E-02
SH-126
94.81
1.84E-02
SH-126
94. 91
9.0DE+01
AM-243
95. 6Z
3.75E-01
AM-Z43
97.1%
200,00
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
5.00E-03
CS-135
58.92
4. 511-03
CS-135
59.22
3.29E-03
CS-135
eo.oz
5.65E-02
SN-126
96. 5%
2.06E-02
SH-126
96. 61
9.931-04
SN-126
96.81
3.05E+01
AH-243
100. OZ
500.00
0.0
NOME
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
2.40E-03
CS-135
60.12
1.42E-03
CS-135
61.4Z
5.00E-04
CS-135
64. 1Z
2.58E-03
SN-126
99. IX
1.71E-05
SH-126
98. 1Z
750.00
0.0
ROHE
O.OZ
0.0
HONE
O.OZ
0.0
MOKE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
2.21E-03
CS-135
60. U
1.31E-03
OS- 135
61.4Z
4.60E-04
CS-135
64. 1Z
6.92E-03
SN-126
99,72
4.47E-05
SH-126
99. 3Z
1000.00
0.0
NOSE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
2.15E-03
CS-135
60.11
1.28E-03
CS-135
61. 4Z
4.49E-04
CS-135
64. 1Z
1.96E-02
SN-126
99. 9Z
1.26E-04
SN-126
99. SZ
1500.00
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
0.02
1.32E-03
CS-135
61.52
4.66E-04
CS-135
64. 2Z
2.10E-05
CS-135
70. 3Z
1. 13E-03
SH-126
100.0Z
2000.00
0.0
mm
O.OZ
0,0
HONE
O.OZ
0.0
HONE
O.DZ
0.0
NONE
O.OZ
0.0
NONE
Q.OZ
0.0
NONE
O.OZ
1.45E-03
CS-135
61.52
5.12E-04
CS-135
64. 22
2.29E-05
CS-135
70. 6Z
1.05E-02
SN-126
100, OS
4000.00
0.0
KOHE
O.OZ
0.0
HONE
O.OZ
0.0
HOSE
O.OZ
0.0
HONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
9.37E-04
CS-135
64.22
4.20E-05
CS-135
71.31
4.92E-07
1C -99
50.22
-------
Table 6.27
tn
cr
TIME (yr)
l.OOE+01
2.00E+01
5.00E+01
l.OOE-tflZ
2.00E+02
5.00E+02
1.00E+G3
2.00E+03
5.00E+03
1.00E-K!4
Dose Equivalent Races (rera/yr) from Drinking Grotmdwatei Contaminated by Radionuclides
Released by Borehole Drilling in BEDDED SALT
1000 Years After Repository Sealing
Drill Hits Repository Water
Leach Rate ~ 10"^ per year
DISTANCE (aetera)
20,00
3.93B-0*
GS-135
57. n
3.96E-04
CS-135
57. 7X
3.95E-04
CS-135
57. 8X
4.83E-03
SR-126
91.81
4.82E-03
Sfi-126
91.92
4.79E-03
SN-126
92.0!
1.25E+02
AM-241
93. IX
3.31E+01
AH-241
76. 5Z
5.96E+00
AM-243
95.01
3.43B+00
AM-243
99.0%
50.00
0.0
NONE
o.oz
0.0
NONE
O.OZ
2.SOE-04
CS- 135
57. 8X
2.49E-04
GS-135
58.0%
2.47E-04
GS-135
58.32
3.04E-03
SN-126
92.0%
3.00E-03
SS-126
92. IX
2.93E-03
SN-126
92. 3Z
3.85E+00
AMh243
95. OX
2.24E+00
AH-243
99. IX
100.00
0.0
HONE
O.OX
0.0
HONE
O.OZ
1.771-04
CS-135
57. 8X
1. 76B-04
GS-135
58. OZ
1. 75E-04
CS-135
58.31
2.15E-03
SH-126
92.01
2.13E-03
SN-126
92.21
2.08E-Q3
SH-126
92.4Z
2.80E+OQ
AH-243
94. 9X
1.60E+00
AM-243
99. 2Z
200.00
6.0
NONE
O.OX
0.0
NONE
O.OX
0.0
NONE
O.OX
1.25E-04
CS-135
57. 9X
1.241-04
CS-135
58.2Z
1.22E-04
CS-135
59. IX
1.51E-03
SN-126
92.21
1.48E-03
SH-126
92.4S
1.38E-03
SN-126
93, OX
1.20E+00
AM-243
99. 2X
500.00
O.O
NONE
0.02
0.0
NONE
O.OX
0.0
NONE
O.OX
0.0
NONE
0.02
0.0
NONE
O.OX
7.71E-05
CS-135
59. IX
7.48E-05
CS-135
60.6X
7.05E-05
CS-135
63 .«
8.95E-04
SH-126
93. 2X
8.21B-04
SN-126
93. 8X
750.00
0.0
HOME
O.OX
0.0
NONE
O.OX
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OX
6.30E-05
CS-135
59. IX
6.12E-05
CS-135
60. 6X
5.77E-05
CS-135
63.4Z
7.41E-04
SN-126
93. 3X
ft. 70E-04
SN-126
93.8X
1000.00
0.0
NONE
O.OX
0.0
HONE
O.OZ
0.0
NOME
O.OX
0.0
HONE
0,01
0.0
NONE
O.OX
5.46E-05
CS-135
59. OX
5.311-05
CS-135
60. 51
5.01E-05
CS-135
63. 3X
6.481-04
SN-126
93. 3X
5.85B-04
SN-126
93, 8X
1500.00
0.0
NONE
0.02
0.0
NONE
0.02
0.0
HONE
O.OZ
0.0
NONE
O.OX
0.0
NONE
O.OX
0.0
NONE
0.02
4.35E-05
CS-135
60. 5X
4.11E-05
CS-135
63. 3X
3.53E-05
CS-135
70. 9X
4.96E-04
SN-126
94. IX
2000.00
0.0
NONE
O.OX
0.0
NONE
0.02
0.0
NONE
O.OZ
0.0
NONE
O.OX
0.0
HONE
O.OX
0.0
NONE
O.OX
3.78E-05
CS-13S
60.4X
3.57E-05
CS-13S
63. 3X
3.061-05
CS-135
70. 9X
4.37E-04
SN-126
94.2Z
4000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
HONE
O.OX
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
2.55E-05
CS-135
63.12
2.20E-05
CS-135
70. 9X
1.83E-05
CS-135
80.BX
-------
Table 6.28
Area (ha*) of the Aquifer Contaminated
Above the Specified Dose Rate Levels
Following Drilling into a Brine Pocket
1000 Years after Sealing
Variable leach rates
Leach Rate Length of time Dose limits (rem/yr)
(per year) after event (yr) 0.5 5 50 500
1C'2 0-500 0000
1000 0.21 0.10 0 0
2000-10000 000
10"3 0-500 0000
1000 0.38 0.33 0.27 0.19
2000 0.33 0.27 0.19 0
5000 2.35 1.51 0.56 0
10000 5.62 3.73 0 0
ID'5 0-500 0000
1000 0.29 0.22 0.12 0
2000 0.25 0.17 0 0
SOOO 1.56 0.05 0 0
10000 3.90 0 0 0
*1 hectare (ha) = ID4 square meters
156
-------
is limited by its solubility. In most previous cases the americum
never reached its solubility limit. Table 6,26 has the highest dose
rate shown on this scenario's tables, 4900 rem/yr for a leach rate of
TO"3 yr"1. The highest dose rate in Table 6.27 (1Q~5 yr"1 leach rate)
is 125 rem/yr, while for 10" yr" leach rate (Table 5.12) it was
1150 rem/yr. Due to the narrowness of the band of contamination
n I
(section 6.3.1), the largest annual dose rate for a 10 yr leach
rate is not seen in Table 6.25. The area contaminated by it
(Table 6.28) is so small that it is insignificant when averaged over
the length of the repository or compared to other areas contaminated.
6.3.2 Release to the aquifer due to faulting
Direct hit on waste
Comparing Tables 6.29, 6.30, 6.31 and 5.22 illustrates the effect
of a varying leach rate on doses resulting from a fault line. As the
leach rate becomes smaller, the maximum dose rate drops and the time
when the maximum dose rate occurs increases.
Maximum Dose Rate Time of Maximum
Reference L (rem/yr) (years)
Table 6.29 10"Z 4200 100
Table 6.30 10"3 3400 200
Table 5.22 10"4 600 500
Table 6.31 10"5 65 500
Table 6.29 shows no dependence of dose on distance, due to the
extremely large leach rate. As soon as the nuclides flow downstream,
they are replaced by fresh leachets until the canisters are emptied
after several hundred years. Sn-126, Am-241, and Am-243 dominate
Table 6.29. Table 6.30 features the same dominant nuclides, with the
addition of Pu-239 at 10,000 years, and all the nuclides have been
removed from the canisters after several thousand years. There is some
157
-------
in
oo
Table 6.29
Dose Equivalent Rates (cem/yr) from Drinking Groundwater Contaminated by RadionucLides
Released by Fault: Hovenent
1000 fenrs After Repository Sealing
Waste DireccLy Affected
Lead) Rate » 10"^ per year
DISTANCE (metern)
TIMS (yr)
l.QQE+01
2.00E+01
5.00E+01
l.OOE+02
2.00B+02
5.00E+02
i.OOE+03
2.00E+03
5.00E+03
l.QOE+04
20.00
3.22E-01
SH-126
58.51
5.04E-D1
SN-126
re. ox
5.16E+02
AM-241
98.02
4.23E+03
AH-241
97. 91
2.22E+Q3
AH-241
97.5%
B.54E+01
AM-241
92.42
2.98E-0H
AM-241
84.21
4.50E-05
AH-241
S5.8Z
1.52E-19
AK-243
35.92
0.0
NONE
0.02
50,00
3.26E-01
SH-12«
57.81
5.67E-01
SN-126
67. 5Z
5.162+02
AH-241
98.0%
4.23E-MJ3
AH-241
97.91
2.2ZE+03
AM-241
97.52
8.54E+01
AH-241
92. «
2.98E-01
AM-241
84.12
4.50B-06
AH-241
55.81
1.52B-19
AM- 243
35. 9Z
0.0
NONE
a. oi
100.00
3.26E-01
^-126
57.SI
5.67E-01
SM-126
67.51
5.16E+02
AH-241
98.01
4. 231+03
AM-241
97.9Z
2.22E+03
AM-241
97. SZ
8.S4E+01
Ati-241
92. «
2.98E-01
AM-241
84. IK
4.50S-Q6
AM-241
55.71
1.52E-19
AM-243
35. 9Z
0.0
HONE
O.OZ
200.00
3.26E-01
SH-126
57.8%
5.67E-01
SH-126
67.51
5.16E+02
AH-241
98.02
4.23E+03
AM-241
97.9Z
2.22E4-03
AM-241
97.5%
8.54E+01
AM-241
92.41
2,988-01
AM-241
84.12
4.50E-06
AH-241
55. 7Z
1.52E-19
AH-243
35. 9 Z
0.0
NONE
0.02
500,00
3.26E-01
SN-126
57.8%
5.67E-01
SN-126
67. 5J
5, 16E«-02
AH-241
98.0%
4.23E+03
AH-241
97.92
2.22E+03
AH-241
97.51
8.54E+01
AH-241
92.41
2.98E-01
AM-241
84.12
4.50E-06
AM-241
55.72
1.52B-19
AM-243
35.92
0.0
NOME
0.02
750.00
3.26E-01
SM-126
57.82
5.67E-01
SH-126
67.51
5.16E+02
AM-241
9«.02
4.23E*03
AW-241
97. 9Z
2.22E+03
AN-241
97.5%
8.54E+01
AH-241
92.42
2.98E-01
AM-241
84.12
4.50E-06
AM-241
55.72
1.52E-19
AM-243
35.92
0.0
H08E
0.02
1000.00
3.26E-01
SH-126
57.8%
5.67E-01
SH-126
67.52
5.16E+02
AM-241
98.02
4.23E-MJ3
AM-241
97.9%
2.22B+03
AM-241
97.5%
8.54E+01
AM-241
92.4%
2.98E-01
AM-241
84.12
4.50E-06
AM-241
55.72
1. 52E-19
AM-243
35.92
0.0
HONE
0,0%
1500.00
3.26E-01
SS-126
57.8%
5.67E-01
SH-126
67.5%
5.16E*02
AM-241
93.02
4.23E+03
AM-241
97.92
2.22E*03
AM-241
97.52
8.54E1-01
AM-241
92.4%
2.98E-01
AM-241
84.1%
4.50E-06
AM-241
55.72
1.52E-19
AM-243
35.92
0.0
HOME
0.0%
2000.00
3.26E-01
SM-126
57.8%
5.67E-at
SM-126
67.52
5.161+02-
AM-241 . 'ri
98. OZ
4.23S+03
AM-241
97.9%
2.22E+03
AH-241
97.32
8.54E+01
AM-241
92.4%
2 . 98E-01
AM-241
84,1%
4.50E-06
AM-241
55.72
1.52E-19
AM-243
35.9%
0.0
NONE
O.OZ
4000.00
3.26E-01
S8-126
57.82
5.67E-01
SN-126
67.52
5.16E+02
AM-241
98.0%
4.23B+03
AM-241
97. 9Z
2". Z2E+03
AM-241
97.51
8.54E+01
AM-241
92.42
2.98E-01
AM-241
84.12
4.50E-06
AM-Z41
55.7%
1.52E-19
AK-243
35.91
0.0
HOME
O.OZ
-------
Table 6.30
Tim (yr)
1.00E+Q1
2.00E+01
5.00E+01
1,DOS*02
2.00E+02
5.00E+02
l.OOE+03
2.0QE+03
5.00E+Q3
t.OOE+04
Doae Equivalent Rates (teai/yr) iron Drinking Ground*ater Contaminated by Hadionuclides
Released by Fault Movement
1000 Yeara After Repository Sealing
Waet* Directly Affected
Leach Rate ™ 10"' per yea*
DI8TAHCS (aetern)
20.00
3.86B-02
SH-126
57.11
6.71E-02
SH-126
75.61
1.26E+OZ
AM-241
98.01
1.97E+03
AH-241
97.9%
3,441+03
AM-241
91.61
3.14E+03
AM-241
96.22
1.25E+03
AM-241
92.11
1.35E*02
AM-241
6B.9I
3.01E+00
AM-243
36.01
1.42E-02
PU-239
36.6%
50.00
3.91E-02
SN-126
56.41
7.66E-02
SM-126
66.31
1.26E+02
AM-241
97.91
1.97E+03
AM-241
97.91
3.45E+03
AM-241
97. 6%
3.141+03
AM-241
96. 2%
1.27E+03
AM-Z41
92.1%
1.68E+02
AM-241
67.51
3.71E+00
AM-243
35. 9%
1. 75E-02
PU-239
36.8Z
100.00
3.91E-02
SH-126
56.4Z
7.66E-02
SH-126
66.31
1.26E+02
AM-241
97.9*
1.97E+03
AM-241
97. 9Z
3.45E+03
AM-241
97.6Z
3.148+03
ftM-241
96, 2%
1.27E+03
AM-241
92.11
1.681+02
AH-241
67. 5%
3.85E+00
AM-243
35.9%
1.81E-02
PU-239
36-81
200.00
3.9il-02
SH-1Z6
56.41
7.66E-02
SH-126
66.31
1.26E+02
AM-241
97. 9X
1.97E+03
AM-241
97.91
3.45E+03
AH-241
97.61
3.14E+03
AH-241
96.2%
1.27E+03
AH-241
92.1%
1.68E+02
AM-241
67.51
3.86E+00
AM-243
35.9%
1.82E-02
PU-239
36.8%
500.00
3.91E-02
S8-126
56.4%
7.66E-02
SH-126
06.31
1.26E+02
AM-241
97, 9Z
1.97E+03
AM-241
97.9%
3.45E+03
AM-241
97.6%
3.14E+03
AM-241
96.2%
1.27E+03
AM-241
92.1%
1.6BE+02
AM-241
67.4X
3.86E+00
AM-243
35.9Z
1.82E-02
PU-239
36.7%
750.00
3.91E-02
SN-126
56.4%
7.66E-02
SH-126
56.3%
1.26E+02
AM-241
97.9%
1.97E+03
AM-241
97.9%
3.45E+03
AM-241
97.6%
3.14E+03
AH-241
96.2%
1.27B+03
AM-241
92,1%
1.68E+02
AM-241
67,4%
3.86E+00
AM-243
35.9%
1.82E-02
PU-239
36.7%
1000.00
3.91E-02
SH-126
56.4%
7.66E-02
SM-126
66.3%
1.26E+02
AM-I41
97.91
1.97E+03
AM-241
97.9%
3.45E+03
AM-241
97.6%
3.14E+03
AM-241
96.2?
1.27E+03
AH-241
92.1%
1.68E+02
AM-241
67.4%
3.86E+00
AM-243
35.9%
1.82E-OZ
PU-339
36.7%
1500.00
3. 912-02
SH-126
5S.4I
7.66E-02
SN-126
66.3%
1.26E+02
AM-241
97. 9S
1.97E+03
AM-241
97.9%
3.45E+03
AM-241
97,6%
3.14E+03
AM-241
96.2%
1.27E+03
AM-241
92.1%
1.68E+02
AH-241
67.4%
3.86E400
AM-243
35.9%
1.82E-OZ
PU-239
36, n
2000.00
3.S1E-02
SN-126
56 .41
7.66E-02
SH-126
66.3%
1.26E+02
AM-241
97.9%
1.97E+03
AM-241
97.9%
3.45E+03
AM-241
97.6%
3.14E+03
AM-2it
96.2%
1.27E+03
AM-241
92.1%
1.58E+02
AM-241
67.4%
3.86E+00
AM-243
35.9%
1.82E-02
PU-239
36.7%
4000.00
3.91E-02
SH-126
56.4%
7.66E-02
SH-126
66.3%
1.26E+02
AM-241
97.9%
1.97E+03
AK-241
97.91
3.45E+03
AM-241
97.61
3.141+03
AH-241
96.2%
1.27E+03
AS-241
92.1%
1.68S+02
AH-241
67.4%
3.86E+00
AH-263
35.9%
1.82B-02
PU-239
36.7%
-------
CT-
O
Table 6.31
Dose Equivalent Rates (ren/yr) from Drinking Groundwater Contaminated by Radionuclidea
Released by Fault Movement
1QOQ Years After Repository Sealing
Haste Direttiy Affected
Leach Rate " 10~" per year
DISIAHCE (inter*)
TIHE (yr)
l.OOE+01
2.001*01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2. DOE +03
5.00E+03
1. ODE +04
20.00
5.42E-04
SH-126
41.41
8.411-04
SH-126
62. ZX
1.42E+00
AM- 241
95.32
2.41E+01
AM-241
95. IS
4.86E+01
AM-241
94,4%
6.76E+01
AH-241
91.61
5.32E+01
AM-241
84.2%
1. 732+01
AH-241
55. 8*
6. 13E+00
AM-243
36.02
4.07E+OQ
PU-239
36.82
50.00
5.52E-04
SN-126
40.62
1.03E-03
SH-126
51. 02
1.42E+00
AH-241
95.32
2.411+01
AM-241
95. IX
4.86E+01
AM-241
94.42
6.76E+01
AM-241
91.62
5.48E+01
AH-241
84.2Z
2.75E+01
AM-241
55.82
I.Q7E+01
AM-243
36.0%
7.Q9E+00
PU-239
36.82
100.00
5.52E-04
SH-126
40.62
.1.038-03
SH-1Z6
51.02
1.42E+00
AM-241
95.3%
2.41E+01
AM-241
95. IX
4.86E+Q1
AM-241
94,42
6.76E+01
AM-241
91.62
5.49E+01
AH-241
84.2!
2.751+01
AM-241
55.81
1.57E+01
AM-243
36.02
1.04E+01
PU-239
36. 8Z
•200.00
5.52E-04
SN-126
40.62
U03E-03
SN-126
51. OX
1.42E+00
AH-241
95. 3X
2.41E+01
AM-241
95. IX
4.86E+01
AM-241
94.42
6.761+01
AH-241
91.62
5.491+01
AM-241
84. 2Z
2.75E+01
AM-241
55.82
1.61E+01
AK-243
36.02
1.491+01
PU-239
36.81
500.00
5.52E-04
SH-126
40.62
1.03E-03
SH-126
51.01
1.42E+00
AH-241
95.32
2.41E+01
AM-241
95. 1Z
4.86E+01
AM-241
94. 4Z
6.761+01
AM-241
91.62
5.491+01
AM-241
84.22
2.75E+01
AM-241
55.82
1.61E+01
AM-243
35.92
1.531+01
PU-239
36.82
750.00
5.52E-04
SH-126
40.62
1.03E-03
SH-126
51.02
1.42E+00
AM-241
95.3.1
2.41E+01
AM-241
95.12
4.86E+01
AH-241
94.42
6.76E+01
AM-241
9),6Z
5.49E+01
AH-241
84.22
2.75E+01
AM-241
55.82
1.61E+01
AM-243
35,92
1.53B+01
PU-239
36.82
1000. 00«
5.52E-04
SN-126
40.62
1.03E-03
SH-126
51.02
1.42E+00
AM-241
95.3*
2.41E+01
AM-241
95.12
4.86E+01
AM-241
94.42
6.76E+01
AM-241
91.61
5.49E+01
AH-241
84.22
2.75E+01
AM-241
55.82
1.61E+01
AM-243
35. n
1.53E+01
PU-239
36.82
1500.00
S.52E-04
SH-126
40. 6Z
l.OJE-03
SH-126
51.02
1.42E+00
AM-241
95. 32
2.41E+01
AN-241
95.12
4.86E+01
AM-241
94.42
6.76E+01
AM-Z41
91.62
5.491+01
AH-241
84.22
2.75E+01
AM-241
55.82
1.61E+01
AH-243
35.92
1.53E+01
PU-239
36,82
2000.00
5.52E-04
SH-126
40.62
1.031-03
SH-126
51.02
1.42E+00
AM-241
95. 3X
2.41E-MJ1
AM-241
95.11
4.86E+01
AH-241
94,42
6.76E+01
AK-241
91.62
5.49E+01
AM-241
84.22
2.76E+01
AM-241
55.82
1.61E+01
AM-243
35. n
1.53E+01
PU-239
36.82
4000.00
5.52E-04
SN-126
40.61
1.031-03
SH-126
51.02
1.42E+OQ
AM-241
95.32
2.41E+01
AM-241
95.12
4.86E+01
AM-241
94.42
6.76E+01
AM-241
91,62
5.49E+01
AM-241
84.22
2.76E+01
AM-241
55.82
I.61E+01
AH-243
35.9%
1.53E+01
PU-239
36.72
-------
dependence on distance in this case, but not as much as with the low
leach rate in Table 6.31. The low leach rate decreases the flow of
nuclides from canister to aquifer. The same nuclides dominate the
table.
Hit on contaminated repository water
The dominant nuc Tides and their migration are the same as in the
base case for all three leach rate values, but the magnitude of the
annual dose rates is different (Tables 6.32, 6.33, 6.34). The maximum
O "I j±
dose rate with a leach rate of 10 yr is 6.3 x 10 rem/yr,
98. OX from Am-241 . The maximum for a leach rate of 10" yr" is
fi -5 -1
3.9 x 10 rem/yr and the maximum for a leach rate of 10 yr is
58,000 rem/yr. The maximum dose rate for a leach rate of 10 yr"'
is 600,000 rem/yr. These doses reflect the entry of nuclides into the
granite tank prior to the occurrence of the fault. The flow of water
is much larger in this case, leading to rapid depletion of the nuclide
inventory. In each case, the highest dose occurs 100 years after the
event and along the downstream side of the aquifer (repository). When
-2 -1
the leach rate is 10 yr , the nuclides enter the tank quickly
and are released along the fault into the aquifer. By 10,000 years
there are only low doses over the first two hundred meters of the
repository, the Am-243 and other nuclides having flowed downstream.
1 -1
When tne leach rate is 10 yr , the waste does not leach as fast,
therefore nuclides remain in the waste to feed the tank for a longer
time. When the leach rate is 10 yr" , the annual dose rates do
not become very small in 10,000 years. The concentration is lower and
the contamination time is longer. Am~241 and Am-243 are prevalent in
all cases, except for Sn-126 very early and Pu-239 at 10,000 years.
6.3.3 Release to the land surface
Tables 6.35 through 6.37 give the annual dose rates resulting from
releases to the land surface by drilling into granite repository water
having leach rates of 10"2, 10"3, and 10"5 yr"1 . Table 5.38
151
-------
fable 6.32
Dose Equivalent Rates (rem/yr) froo Drinking Groundwater Contaminated by Radiotmclides
Released by Fault Movement
1000 Years Afrer Repository Scaling
Repository Water Affected
Leach R«te ~ 10"^ per year
DISTANCE (meters)
TIME (yr)
l.OOE+01
2.0QE+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
S.OOE+03
1.00E+04
20.00
7.63E+02
SH-126
54. OX
4.97E+02
SN-126
89.31
3.42E+06
AM-241
95.4Z
S.31E+06
AM-241
9S.1X
3.81E+06
AH-241
94 .4%
1.5&E+06
AM-241
91. 6Z
1.21E+D2
AM-Z41
84.21
7.48E-04
AM-241
55.it
2.53E-17
AM-243
36.0%
0.0
NONE
0.0%
50.00
7.92B+02
SH-126
52. «
7.24E+Q2
SN-126
61.4%
3.42E+06
AM-241
95.4*
6. 3 IE +06
AM-241
95. IX
3.81E+06
AM-241
94, 4X
1.56E+06
AH-241
91. 6%
5.63E+05
AM-241
84.21
1.32E+05
AM-241
55. 8X
2.46E-11
AH-243
36.0%
4.92E-34
PU-239
78.5X
100.00
7,921+02
SN-126
52.11
7.24E+02
SH-126
61.4%
3.42E+06
AH-241
95.4X
6.31E+06
AM-241
95. IX
3.81B+06
AM-241
94. 4X
1.56E+06
A»-241
91. 6X
5.63E+05
AM-241
S4.2X
1.32E+05
AH-241
55.8X
3.76E-01
AH-243
36.0%
5.07E-23
PU-239
36. 3Z
200.00
7.92E+02
SN-126
52.1%
7.24E+02
SN-126
61.42
3.42E+06
AM-241
95.4X
6.31E+06
AM-241
95. IX
3.81E+06
AM-241
94.41
1.56E+06
AM-241
91. 6%
5.63K+05
AM-241
84.2%
1.32E+05
AM-241
55. 8X
3.01E+04
AM-243
36. OX
1.71E-02
PU-239
36.81
500.00
7.92E+02
SN-126
52. IX
7.24E+02
SN-126
S1.4X
3.42E+06
AM-241
95.4Z
6.31S+06
AM-241
95. IX
3.31E4-06
AM-241
94, 4X
1.56E*06
AM-241
91. 6X
5.63E+05
AM-241
84. 2X
1.32E+05
AM-241
55. 8X
3.01E+04
AM-243
36. OZ
1.49E+04
PU-239
36. 8X
750.00
7.92E+02
SN-126
52. IX
7.24E*02
SN-126
61. 4%
3.42E+06
AM-241
95. 4X
6.31E+06
AH-241
95.1%
3.81R+06
AM-241
94.4%
1.56E+06
AM-241
91.6%
5.63E+05
AM-241
84.21
1.32E+05
AM-241
55.8%
3.01E+04
AM-243
36.0Z
1.49E+04
PO-239
36.8!
1000.00
7.921+02
SN-126
52. IX
7.24E+02
SN-126
61.4Z
3.42E+06
AM-241
95.4%
6.31E+06
AM-241
95. IX
3.81E+06
AM-241
94.4X
1.56E+06
AM-241
91.6%
5.63E+05
AM-241
84.2X
1.32E+05
AM-241
55. m
3.01E+04
AM-243
36.0%
1.49E+04
PO-239
36.8%
1500.00
7.92E+02
SN-126
52.1%
7.24E+02
SN-126
61.4%
3.4ZE+06
AM-241
95.4%
6.31E+06
AM-241
95. IX
3.S1E+06
AM-241
94.4X
1.56E+06
AM-241
91.6%
5.63E+05
AM-241
84.2%
1.32E+05
AM-241
55. 8X
3.01E+04
AM-243
35. 9X
1.49E+04
P0-239
36.81
2000.00
7.92E+02
SN-126
52. IX
7.24E+02
SN-126
61.4%
3.42E+06
AM-241
95.41
6.31E+06
AH-241
95.11
3. 8 IE +05
AM-241
94.4%
1.56E+06
AM-241
91.6%
5.63E+05
AH-241
84.2%
1.32E+05
AN-241
55.8%
3.01E+04
AH-243
35.9%
1.49E+04
PU-239
36.8%
4000.00
7.92E+02
SN-126
52.1%
7.24E+02
SN-126
61.4%
3.42E+06
AM-241
95.4X
6. 3 IE +06
AM-241
95.1%
3. 8 IE +06
AM-241
94 ,«
1.56E+06
AM-241
91.6Z
5.63E+05
AM-241
84.2%
1.32E+05
AM-241
55.8%
3.01E+04
AM-243
35. 9X
1.49E+04
PU-239
36.8%
-------
Table 6.33
01
CO
TIMS (yr)
l.QOE+01
2.00E+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+Q3
5.00E+03
l.OQE+04
Dose Equivalent Rates
-------
cn
•£>
Table 6.34
Dose Equivalent Ratea (rem/yr) from Drinking Groundwater Contaminated by Radionuclidea
Released by Fault Movement
1000 Years After Repository Sealing
Repository Hacer Affected
Leach Rate « 10"' per year
DISTANCE (meters)
TIHE (yr)
1.0QE+Q1
2.00E+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5. 001! '03
i,,:.D3-i04
20.00
6.88E+OQ
SN-126
53.9%
4.56E+00
SH-126
88.62
3.07E*04
AM-241
95.4%
6.00E+04
AM-241
95. 12
4.16E+Q4
AM-241
94.41
2.46E+04
AM-241
91.62
8.39E+03
AM-241
84.21
2.76E+03
AM-241
55. 8X
9.67E+02
AM-243
36.01
6.43E402
PU-239
36.81
50.00
7,14E*Q0
SH-126
51,92
6.601+00
SH-126
61.2*
3.07E+04
AM-Z41
95.42
6.00E+04
AM-241
95.11
4.16E+04
AM-Z41
94.42
2.46E+D4
AM-241
91. 6X
1.37E+04
AM-241
84.21
5.S5E+03
AM-241
S5.8Z
t.70E*03
AM-243
36.0Z
1.13E+03
PU-239
36.8;
100.00
7.14E+00
Si- 126
51.91
6.60E+00
SH-126
61. 2*
3.07E+04
AH-241
95.4X
6.00E+04
AH-241
95. 1Z
4.16E+04
AH-241
94. 4Z
2.46E+04
AM-241
91.62
1.37E+04
AH-241
84.21
5.55E+03
AM-241
55.81
2.54E+03
AM-243
36. 01
1.69E+03
PU-239
36.81
200.00
7.14E+00
SH-126
51.9%
6.60E+00
SH-126
61.2S
3.07E+04
AM-241
95.4%
6.00E+04
AM-241
95.12
4. 161*04
AM-241
94. 4Z
2.46E+04
AM-241
91.62
1.37E+04
AM-241
84.22
5.56E+03
AM-241
55.82
2.87E+03
AM-243
36. 02
2.50E«03
PU-239
36.82
500.00
7.14E*00
SH-126
51.92
5.50E*OO
SH-126
61.22
3.07E+04
AM-241
95.42
6.00E*04
AM-241
95.12
4.161*04
AM-241
94.42
2.46EWJ4
AM-241
91.62
l.37E»04
AM-241
84. 2Z
5.56E*03
AM-241
55.81
2.87E+03
AM-243
35.92
2.688+03
PU-239
36.82
750.00
7.148*00
5H-126
51.91
6 . 60E+00
SH-126
61.21
3.07E+04
AM-241
95.42
6.00E+04
AM-241
95. 1Z
4.16E*04
AM-241
94,42
2.46E+04
AJt-241
91,62
1.37E*04
AM-241
84.22
5.56E+Q3
AM-241
55.81
2.8?g*03
AU-243
35.91
2.68E*03
PU-Z39
36. 82
1000.00
7.14E+00
SN-126
51.92
6.60E+00
SH-126
61.22
3.07E+04
AM-241
95.42
6, DOE +04
AM-241
95. 1Z
4.16E-MJ4
AM-241
94.4Z
2.46E+04
AM-241
91,62
1.37E+04
AM-241
84.22
5.56E+03
AM-241
55.81
2.87E+03
AM-243
35.92
2.68E-I-03
PU-239
36.82
1500.00
7. 141+00
SH-126
51.92
6.60E+00
SH-126
61.22
3.07E+04
AM-241
95.42
6.001+04
AM-241
95.11
4.16E+04
AM-241
94.42
Z.46E+04
AW-241
91.62
1.37E+04
AM-241
84.22
5.56E+03
AM-241
55.82
2.87E+03
AM-243
35.92
2.68E+03
PU-239
36.82
2000.00
7.14B+00
SH-126
51.92
6.60E+OD
SH-126
61.22
3.07E+04
AH-241
95.42
6.00E+04
AH-241
95.lt
4.16E+04
AH-241
94.42
2.45E+04
AH-241
91.62
1.37E+04
AM-241
84.22
5.56S+03
AM-241
55.82
2.87E+03
AH-243
35.92
2.68E+03
PU-239
36.82
4000.00
7.14E+00
SH-126
51.92
6.60E+00
SH-126
61.22
3.07E+04
AM-241
95.42
6.00E+04
AH-241
95.12
4.16E+04
AM-241
94,42
2.46E+04
AM-241
91.61
1.37E+04
AM-241
84.2%
5.56E+03
AM-241
55.82
2.87E+03
AH-243
35.92
2.68E+03
PU-239
36.72
-------
Table 6.35
Dose Equivalent Rates (rem/yr) Croa Breathing Air Contaminated by Rsdionuclides
Released by Borehole Drilling in GRANITE
1000 Year* After Repository Sealing
Drill Hits Repository Hater
Leach Rate - 10"^ per year
DISTANCE (aetera)
TIME (yr)
l.OOE+01
2.00E+01
5.00E-I-01
cn
tn
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.001+03
5.00E+03
l.OOE+04
20.00
1.47E+Q1
AM-241
98, 2Z
1.44E+01
AM-241
98.2%
1.35E+01
AM-241
98.12
1.22E+01
AM-241
98.0%
l.OOE+Ol
AM-241
97.72
5.54E+00
AM-241
96.62
2.09E+00
AM-241
93.32
3.36E-01
AM-241
77.2%
1.35E-02
AM-243
95,4%
6.541-04
AM-243
100. OX
50.00
3.88E+00
AM-241
98.2%
3.80E+00
AM-241
98.22
3.58E+OQ
AM-241
98.1%
3.24E+00
AM-241
98.0%
2.65E+00
AM-241
97. 7%
1.47E+00
AM-241
96. 6Z
5.53E-01
AM-241
93. 3Z
8.89E-02
AM-241
77.2%
3.56E-03
AM-243
95.4%
1.73B-04
AM-243
100.02
100,00
1.40E400
AH-241
98.2%
1.381+00
AM-241
98.2%
1.30E+00
AM-241
98. IX
1. 17E+00
AM-241
98.02
9.611-01
AM-241
97. n
5.31E-01
AM-241
96.61
2.00E-01
AM-241
93. 3*
3.22E-02
AM-241
77.2%
1. 298-03
AK-243
95.4Z
6.27E-05
AM-243
100. OZ *
200,00
5.03E-01
AM-241
98.21
4.93B-Q1
AM-241
98.2%
4. 54E-01
AM-241
98.1%
4.20E-01
AM-241
98.02
3.44S-01
AM-241
97,72
1.90E-01
AM-241
96,62
7.17E-02
AM-241
93.3%
1. 15E-02
AM-241
77. 2Z
4.62S-04
AM-243
95.4Z
2.24E-05
AM-243
100. OZ
500.00
1.26E-01
AK-241
98.22
1.23E-01
AM-241
98.22
1.16E-01
AM-241
98. 1Z
1.05E-01
AM-241
98.0%
8.61K-02
AM-241
97.7%
4.75E-02
AM-241
96.61
1.79E-02
AM-241
93.3%
2.88E-03
AM-241
77. 2%
1.15E-04
AM-243
95.4%
5.61E-06
A«-243
100. OZ
750.00
6.71E-02
AM-241
98.2%
6.581-02
AM-241
98.2%
6.19B-02
AM-241
98.1%
5.60E-02
AM-241
98.02
4.59E-02
AM-241
97.71
2.54E-02
AH-241
96.61
9.57E-03
AM-241
93.3%
1.54E-03
AH-241
77.2%
6.16E-05
AM-243
95,4%
2.99E-06
AM-243
100.02
1000.00
4.26E-02
AM-241
98.2%
4.18E-02
AM-241
93.2%
3.94E-02
AM-241
98. 1Z
3.56E-02
AM-241
98.02
2.92K-02
AN-241
97. 7%
1.618-02
AM-241
96.6Z
6.08E-03
AM-241
93.3%
9.78E-04
AH-241
77. 2%
3.92E-05
AM-243
95. 4Z
1.90E-06
AM-243
100. OZ
1500.00
2.22E-02
AH-241
98. 2%
2.18E-OZ
AH-241
98.2%
2.05E-OZ
AH-241
98. 1Z
1.86E-02
AM-241
98.02
1,521-02
AM-241
97.72
8.40E-03
AM-241
96.6;
3.17E-03
AM-241
93.3%
5.10E-04
S5H241
77.2%
2.04E-05
AH-243
95.4%
9.92E-07
AM-243
100.0%
2000.00
1,381-02
AH-241
98,2%
1.34E-02
AM-241
98. 2%
1.28E-02
AM-241
98.1%
1.16E-02
AM-241
98,0%
9.48E-03
AM-241
97. 7%
5.24E-03
AM-241
96, 6%
1.98E-03
AM-241
93.3%
3.181-04
AM-241
77.2%
1.27E-05
AM-243
95.42
6.18E-07
AM-243
100. OZ
4000.00
4.22E-03
AM-241
98.2%
4.13E-03
AH-241
98.2%
3.89E-03
AM-241
98.1%
3.52E-03
AH-241
98.02
2.89E-03
AH-241
97. 7Z
1.59E-03
AH-241
96. 6Z
6.01E-04
AM-241
93.3%
9.67E-OS
AH-241
77.2%
3.87E-06
AH-243
95.42
1.88E-07
AM-243
100.0%
-------
Table 6.36
Dose Equivalent Rates (rem/yr) from Breathing Air Contaminated by Radionuclides
Released by Borehole Drilling in GRANITE
1000 Years After Repository Sealing
Drill Hits Repository Water
Leach Rate - 10~3 per year
DISTANCE (meters)
TIME (yr)
l.OOE+01
2.00E+01
5.00E+01
l.OOE+02
CT>
O1
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
20.00
5.81E+00
AM-241
98.22
5.69E+00
AM-241
98.22
5.36E+00
AM-241
98.12
4.85E+00
AM-241
98.02
3.98E+00
AM-241
97.72
2.20E+00
AM-241
96.62
8.29E-01
AM-241
93. 32
1.33E-01
AH-241
77.22
5.34E-03
AM-243
95.42
2.59E-04
AM-243
99.92
50.00
1.54E+00
AM-241
98. 22
1.50E+00
AM-241
98.22
1.42E+00
AH-241
98. 11
1.28E+00
AM-241
98.02
1.05E+00
AH-241
97.72
5.80E-01
AH-241
96.62
2.19E-01
AH-241
93.32
3.52E-02
AH-241
77.22
1.41E-03
AH-243
95.42
6.85E-05
AH-243
99.92
100.00
5.56E-01
AH-241
98.22
5.45E-01
AM-241
98.22
5.13E-01
AM-241
98.12
4.65E-01
AM-241
98.02
3.81E-OL
AM-241
97.72
2.10E-01
AM-241
96.62
7.93E-02
AM-241
93.32
1.28E-02
AH-241
77.22
5.11E-04
AM-243
95.42
2.48E-05
AM-243
99.92
200.00
1.99E-01
AM-241
98.22
1.95E-01
AM-241
98.22
1.84E-01
AM-241
98.12
1.66E-01
AM-241
98.02
1.36E-01
AM-241
97.72
7.53E-02
AM-241
96.62
2.84E-02
AM-241
93.32
4.57E-03
AM-241
77.22
1.83E-04
AM-243
95.42
8.89E-06
AM-243
99.92
500.00
4.98E-02
AM-241
98.22
4.88E-02
AH-241
93.22
4.60E-02
AH-241
98. 12
4. 16E-02
AH-241
93.02
3.41E-02
AM-241
97.72
1.88E-02
AH-241
96.62
7.10E-03
AH-241
93.32
1. 14E-03
AH-241
77.22
4.58E-05
AM-243
95.42
2.22E-06
AH-243
99.92
750.00
2.66E-02
AM-241
98.22
2.60E-02
AM-241
98.22
2.45E-02
AM-241
98.12
2.22E-02
AM-241
98.02
1.82E-02
AM-241
97.72
l.OOE-02
AM-241
96.62
3.79E-03
AM-241
93.32
6.09E-04
AM-241
77.22
2.44E-05
AM-243
95.42
1.19E-06
AH-243
99.92
1000.00
1.69E-02
AM-241
98.22
1.66E-02
AM-241
98.22
1.56E-02
AM-241
98.12
1.41E-02
AH-241
98.02
1.16E-02
AM-241
97.72
6.39E-03
AM-241
96.62
2.41E-03
AM-241.
93.32
3.87E-04
AM-241
77.22
1.55E-05
AM-243
95.42
7.54E-07
AM-243
99.92
1500.00
8.81E-03
AM-241
98.22
8.63E-03
AM-241
98.22
8.13E-03
AM-241
98.12
7.36E-03
AM-241
98.02
6.03E-03
AM-241
97.72
3.33E-03
AM-241
96.62
1.26E-03
AH-241
93.32
2.02E-04
AM-241
77.22
8.09E-06
AM-243
95.42
3.93E-07
AH-243
99.92
2000.00
5.49E-03
AM-241
98.22
5.38E-03
AM-241
98.22
5.06E-03
AM-241
98.12
4.58E-03
AM-241
98.02
3.76E-03
AM-Z41
97.72
2.07E-03
AM-241
96.62
7.83E-04
AM-241
93.32
1.26E-04
AM-241
77.22
5.04E-06
AM-243
95.42
2.45E-07
AM-243
99.92
4000.00
1.67E-03
AM-241
98.22
1.64E-03
AM-241
98.22
1.54E-03
AH-241
98.12
1.40E-03
AM-241
98.0%
1.14E-03
AM-241
97.72
6.31E-04
AM-241
96.62
2.38E-04
AM-241
93.32
3.83E-05
AM-241
77.22
1.53E-06
AM-243
95.42
7.46E-08
AM-243
99.92
-------
Tattle 6.37
TIME (yr)
l.OOE+01
2.00E+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
LOOK+04
Doae Equivalent Rates (rem/yr) from Breathing Air Contaminated by Radionuclidea
Released by Borehole Drilling in GRANITE
1000 Yeara After Repository Sealing
Drill Hits Repository Water
Leach Rate « 10~' per year
DISTANCE (meters)
20.00
7.37E-02
AM-241
98. IZ
7.23E-02
AM-241
98. OZ
6.81E-02
AM-241
98. OZ
6.16E-02
AM-241
97. 9Z
5.05E-02
AM- 241
97. 6X
2.79E-02
AM-241
96.42
1.06E-02
AM-241
92. 9Z
1.72E-03
AM-241
75. 9Z
7.24E-05
AM-243
89. IX
3.55E-06
AM-243
92.61
50.00
1.95E-02
AM-241
98. 1Z
1.91E-02
AM-241
98.02
1.80E-02
AM-241
98, OJ
1.63E-02
AM-241
97. 9Z
1.33E-02
AM-241
97. 6Z
7.37E-03
AM-241
96.42
2.79E-03
AM-241
92. 9Z
4.54E-04
AM-241
75. 9*
1.91E-05
AM-243
89. IX
9.37E-07
AM-243
92.62
100.00
7.06E-03
AM-241
98. 1Z
6.92E-03
AM-241
98. OZ
6.52E-03
AM-241
98. OZ
5.90E-03
AM-241
97. 9Z
4.83E-03
AM-241
97. 6Z
2.67E-03
AM-241
96.42
1.01E-03
AM-241
92.92
1.64E-04
AM-241
75. 9Z
6.93E-06
AM-243
89. IX
3.40E-07
AH- 243
92.62
200.00
2.53E-03
AM-241
98. IZ
2.48E-03
AM-241
98. OZ
2.33E-03
AM-241
98. OZ
2.11E-03
AM-241
97. 9Z
1.73E-03
AM-241
97. 62
9.56E-04
AM-241
96.42
3.62E-04
AM-241
92. 9Z
5.88E-05
AM-241
75.92
2.48E-06
AM-243
89. IX
1.22E-07
AM-243
92.62
500.00
6.32E-04
AM-241
98.12
6.19E-04
AM-241
98.02
5.83E-04
AM-241
98.02
5.28E-04
AM-241
97.92
4.33E-04
AM-241
97.62
2.39B-04
AM-241
96.42
9.05E-05
AM-241
92.92
1.47E-05
AM-241
75.92
6.21E-07
AM-243
89. IX
3.04E-08
AM-243
92.62
750.00
3.37E-04
AM-241
98.12
3.31E-04
AM-241
98.12
3.11E-04
AM-241
98. OZ
2.82E-04
AM-241
97.92
2.31E-04
AM-241
97. 6Z
1.28E-04
AM-241
96.42
4.83E-05
AM-241
92. 9Z
7.85E-06
AM-241
75.92
3.31E-07
AM-243
89. IX
1.62E-08
AM-243
92.62
1000.00
2.14E-04
AM-241
98. IZ
2.10E-04
AM-241
98. OZ
1. 98E-04
AM-241
98. OZ
1.79E-04
AM-241
97. 9Z
1.47E-04
AM-241
97.62
8.UE-05
AM-241
96.4Z
3.07E-05
AM-241
92. 9Z
4.99E-06
AM-241
75.92
2.11E-07
AM-243
89. IZ
1.03E-08
AM-243
92.62
1500.00
1.12E-04
AM-241
98.12
1.10E-04
AM-241
98.02
1.03E-04
AM-241
98.02
9.34E-05
AM-241
97.92
7.65E-05
AH-241
97.62
4.23E-05
AM-241
96.42
1.60E-05
AM-241
92.92
2.60E-06
AM-241
75.92
1.10E-07
AM-243
89.12
5.38E-09
AM-243
92.62
2000.00
6.96E-05
AM-241
98.12
6.82E-05
AM-241
98.02
6.43E-05
AM-241
98. OZ
5.82E-05
AM-241
97.92
4.77E-05
AM-241
97. 6Z
2.64E-05
AM-241
96. 4Z
9.97E-06
AM-241
92.92
1.62E-06
AM-241
75. 9Z
6.84E-08
AM-243
89. IX
3.35E-09
AM-243
92. 6Z
4000.00
2.12E-05
AM-241
98.12
2.08E-05
AM-241
98.02
1.96E-05
AM-241
98. OZ
1.77E-05
AM-241
97.92
1.45E-05
AM-241
97. 6Z
8.02E-06
AM-241
96.42
3.03E-06
AM-241
92.92
4.93E-07
AM-241
75. 9Z
2.08E-08
AM-243
89. IX
1.02E-09
AM-243
92.62
-------
gives the annual dose rates for a leach rate of 10 yr . Tables 6.38
through 6.40 give the comparable dose rates from drilling into a brine
pocket. Table 5.34 is the comparable table for a leach rate of
10"4yr"1.
In both granite and salt, the annual dose rates are higher for
higher leach rates. In granite, the maximum dose rates go from
-2 -1 -I5 -1
15 rem/yr for 10 yr leaching to 0.07 rem/yr for 10 yr
leaching; in salt, they go from 0.4 to 0.02 rem/yr for the same leach
rate range.
6.4 Effectof Varying the Retardation Factors
The annual dose rate from a nuclide depends on the retardation
factor "k" primarily through the "U" term (equations 4.41, 4.42, 4.43,
and 4.45) which imposes the obvious requirement that there is no dose
from a nuclide at places the nuclide has not reached. We might con-
sider that nuclides moving very slowly because of a high retardation
factor would be concentrated because the same amount of nuclide would
reach the aquifer and be confined to a smaller volume. However, in the
real situation, the high retardation factor occurs because the nuclide
is largely adsorbed on rock and not available to the water, so that the
nuclide concentration in water that it reaches is affected only
secondarily.
In the following sections, we consider, separately, release sce-
narios using retardation factors of one and higher-than-base-case
retardation factors.
When the retardation factor is one, all nuclides move with the
speed of the groundwater, i.e., 2.1 m/yr. Accordingly, all nuclides
reach the first dose distance of 20 meters in ten years so that early
annual dose rates are much higher than they are in the base case where
the most important nuclide, Am-241, takes 950 years to travel 20 meters.
168
-------
Table 6.38
Dose Equivalent Rates (rem/yr) from Breathing Air Contaminated by Radionuclidea
Released by Borehole Drilling in SEDDED SALT
1000 Years After Repository Sealing
Drill Hits Repository Hater
Leach Rate » 10~2 per year
DISTANCE (meters)
TIME (yr)
l.OOE+01
2.00E+01
5.00E+01
l.OOE+02
2.00E+Q2
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
i.OOE+04
20.00
4.11E-01
AH-241
63. 7Z
3.95E-01
AM-241
64. 9Z
3.53E-01
AM-241
68.41
2.97E-01
A«-24l
73. 61
2.20E-01
AM-241
81. OZ
1. 12E-0.1
AM-241
87. 2%
4.45E-02
AM-241
79, 9%
9.64E-03
AM-243
51.0Z
8.35E-04
AM-243
98. 7Z
4.19E-05
AM-243
100. OZ
50,00
1.09E-01
AM-241
63. 1%
1.05E-01
AH-241
64.91
9.33E-02
AM-241
68.4Z
7.85E-02
AM-241
73.61
5.83E-02
AM-241
81.0%
2.95E-02
AM-241
87.21
1.18E-02
AM-241
79. 9Z
2.55E-03
AM-243
51.0Z
2.21E-04
AM-243
98. 7Z
I. HE-OS
AM-243
100. OZ
100.00
3.94E-02
AM-241
63. 7Z
3.791-02
AM-241
64. 9Z
3.38E-02
AM-241
68.41
2.84E-02
AM-241
73. 6Z
2.11E-02
AM-241
81. OZ
1.07E-02
AM-241
87. 2%
4.261-03
AM-241
79. 9Z
9.23E-04
AM-243
51.0Z
7.99E-05
AM-243
98. 7Z
4.01E-06
AM-243
100, OZ
200.00
1.41E-02
AM-241
63. 7Z
1.36E-02
AK-241
64.91
1.21E-02
AM-241
68.4Z
1.02E-02
AM-241
73. 6Z
7.56E-03
AM-241
81. OZ
3.83E-03
AM-241
87. 2Z
1.52S-03
AM-241
79. 9Z
3.30E-04
AM-243
51. OZ
2.86E-05
AM-243
98. 7Z
1.44E-06
AM-243
100. OZ
500.00
3.53E-03
AM-241
63. 7Z
3.39E-03
AM-241
64. 9%
3.03E-03
AM-241
68.41
2.55E-03
AM-241
73. 6Z
1.89E-03
AH-241
81. OZ
9.58E-04
AM-241
87, 2£
3.81E-04
AM-241
79. 9Z
8.26E-05
AM-243
51. OZ
7.16E-06
AM-243
98. 7Z
3.59E-07
AM-243
100. OZ
750.00
1.88E-03
AM-241
63.7%
1.81E-03
AM-241
64.91
1.62E-03
AM-241
68.4Z
1.36E-03
AM-241
73. 6Z
1.01E-03
AM-241
81, OZ
5.11E-04
AM-241
87, 2Z
2.04E-04
AM-241
79. 9Z
4.41E-05
AM-243
51, OZ
3.82E-06
AM-243
98. 7Z
1.92E-07
AM-243
100. OZ
1000.00
1.20E-03
AM-241
63. 7Z
1. 15E-03
AM-241
64.91
1.03E-03
AM-241
68.4Z
8.63E-04
AM-241
73. 6Z
6.41E-04
AM-241
81, OZ
3.25E-04
AM-241
87.2%
1.29E-04
AM-241
79, 9Z
2.80E-05
AM-243
51, OZ
2.43E-06
AM-243
98. 7Z
1.22E-07
AM-243
100. OZ
1500.00
6.241-04
AM-241
63. 7Z
5.99E-04
AM-241
64.91
5.35E-04
AM-241
68.41
4.50E-04
AM-241
73. 6Z
3.34E-04
AM-241
81.01
1.69E-04
AM-241
87. 2Z
6.74E-05
AM-241
79.91
1.46E-05
AM-243
51. OZ
1.27E-06
AM-243
98. 7Z
6.36E-Q8
AH-243
100. OZ
2000,00
3.88E-04
AM-241
63. 7Z
3,731-04
AM-241
64. 9Z
3.33E-04
AM-241
68.4Z
2.80E-04
AM-241
73. 6Z
2.08E-04
AM-241
81. OZ
1.06E-04
AH-241
87. 2Z
4.20E-05
AM-241
79. 9Z
9.10E-06
AM-243
51. OZ
7.38E-07
AM-243
98. 7Z
3.96E-08
AM-243
100. OZ
4000.00
1.18E-04
AM-241
63. 7Z
1.14E-04
AM-241
64.9Z
1.01E-04
AM-241
68 ,4Z
8.54E-05
AM-241
73. 6Z
6.34E-05
AM-241
81.0Z
3. 2 IE-OS
AM-241
87. 2Z
1.28E-05
AM-241
79. 9Z
2.77E-06
AM-243
51. OZ
2.40E-07
AM-243
98. 7Z
1.21E-08
AM-243
100. OZ
-------
Table 6.39
Dose Equivalent Rates (rsm/yr) from Breaching Air Contaminated by Radionuclidea
Released by Borehole Drilling in BEDDED SALT
1000 Years After Repository Sealing
Drill Hit* Repository Water
Leach Rate » 10~3 per year
DISTANCE (meters)
TIME (yr)
l.OOE+01
2.00E+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
S.OOE+03
l.OOE+04
20.00
3.57E-01
AM-241
73, 3Z
3.46E-01
AM-241
74.31
3.141-01
AM-241
76, 9Z
2.71E-01
AM-241
80.5X
2.09E-01
AM-241
85.31
1,111-01
AM-241
87,91
4.45E-Q2
AM-241
79.93;
9.64E-03
AM-243
51. OZ
8.35E-04
AM-243
98. 7X
4.19E-05
AM-243
100. OX
50.00
9.44E-02
AM-241
73. 3Z
9.13E-Q2
AM-241
74. 3Z
8.30E-02
AM-241
76. n
7.17E-02
AH-241
80.51
5.53E-02
AM-241
85. 3Z
2.93E-02
Att-241
87. n
1. 18S-02
AM-241
79. 9Z
2.55E-03
AM-243
51. OZ
2.21E-04
AM-243
98.71
1. HE-OS
AM-243
IOO.OZ
100.00
3.42E-02
AM-241
73. 3Z
3.31E-02
AM-241
74. 3Z
3.01E-02
AM-241
76. n
2.60E-02
AM-241
80. 51
2.00E-02
AM-241
85. 3Z
1.061-02
AM-241
87. 9Z
4.26E-03
AM-241
79, 9%
9.23S-04
AM-243
51. OZ
7.99E-05
AM-243
98. 7X
4.01E-06
AM-243
100.02
200.00
1.22E-02
AM-241
73.31
1.18E-02
AM-241
74.31
1.08E-02
AM-241
76,91
9.30E-03
AM-241
80. 5Z
7.17E-03
AM-241
85. 3Z
3.801-03
AM-241
87, 9Z
1.52E-03
AM-241
79.9%
3.30E-04
AM-243
51. OZ
2.86E-05
AM-243
98. 7Z
1.44E-06
AM-243
100. OX
500.00
3.06E-03
AM-241
73. 3Z
2.96E-03
AH-241
74. 3Z
2.691-03
AM-241
76.91
2.33E-03
AM-241
80. 5Z
1.79E-03
AM-241
85. 3Z
9.50E-04
AM-241
87. 9S
3.81E-04
AM-241
79. 9X
8.26E-05
AM-243
51. OZ
7.16E-06
AM-243
98. 7Z
3.59E-07
AM-243
IOO.OZ
750.00
1.63E-03
AM-241
73. 3X
1.58E-03
AM-241
74. 3Z
1.44S-03
AM-241
76, 9Z
1.24S-03
AM-241
80.51
9.57E-04
AM-241
85.31
5.07E-04
AM-241
87. 91
2.03E-04
AM-241
79. 9X
4.41E-05
AM-243
51. OZ
3.82E-06
AM-243
98,71
1. 92E-07
AH-243
100, OX
1000,00
1.04E-03
AM-241
73. 3Z
l.OOE-03
AM-241
74. 3X
9.14E-04
AM-241
76. 9X
7.89E-04
AM-241
80. 5Z
6.09E-04
AM-241
85. 3Z
3.22E-04
AM-241
87.91
1.29E-04
AM-241
79. 9Z
2.801-05
AM-243
51. OZ
2.43E-06
AM-243
98. 7X
1.22E-07
AM-243
100. OX
1500.00
5.41E-04
AM-241
73. 37.
5.24E-04
AM-241
74. 3Z
4.76E-04
AH-241
76. 9Z
4.11E-04
AM-241
80. 5Z
3.17E-04
AM-241
85. 3Z
1.68E-04
AM-241
87. 9X
6.74E-05
AM-241
79. 9X
1.46E-OS
AM-243
51. OZ
1.27E-06
AM-243
98. 7 J
6.36E-08
AM-243
IOO.OZ
2000.00
3.37E-04
AM-241
73. 3Z
3.26E-04
AM-241
74. 3X
2.97E-04
AM-241
76,91
2.561-04
AM-241
80. 5Z
1.98E-04
AM-"241
85. 3Z
1.05E-Q4
AM-241
87. 9X
4.201-05
AM-241
79. 9Z
9.10E-06
AH-243
51. OZ
7.88E-07
AM-243
sa. n
3.96E-08
AM-243
100. OX
4000.00
1.03E-04
AM-241
73. 3Z
9.93E-05
AM-241
74. 3Z
9.03E-05
AM-241
76, 9Z
7.80E-05
AM-241
80. 5Z
6.02E-05
AM-241
85. 3X
3.19E-05
AM- 241
87. 9Z
1.28E-05
AM-241
79.9X
2.77E-06
AM-243
51.01
2.40E-07
AM-243
98. 7Z
1.21E-08
AM-243
100. OX
-------
Table 6.40
TIME (yr)
l.OOE-MJl
2.00S+01
5.00E+01
l.OOE+02
2.00E+02
5.QOE+Q2
l.OOE+03
2.00E+03
5.00E+Q3
l.OOE+04
Dole Equivalent Rate* (rem/yr) from Breathing Air Contaminated by Had ionuc tides
Released by Borehole Drilling in BEDDED SALT
1000 Yeare after Repository Sealing
Drill Hit* Repository Hater
Leach rate » IQ~5 pgr year
DISTANCE (meters)
20.00
2.14E-02
AM-241
73.3%
2.07E-02
AH-241
74.3%
1.88E-02
AM-241
76.91
1.63E-02
AM-241
80.5%
1.26E-02
AM-241
85.3%
6.65E-03
AM-241
87.9%
2.67E-03
AM-241
79.9%
5.78E-04
AM-243
51.0%
5.01E-05
AM-243
98.7%
2.52E-06
AM-243
100. OZ
50.00
5.66E-03
AM-241
73.3%
5.48E-03
AM-241
74.31
4.98E-03
AM-241
76.9%
4.30E-03
AH-241
80,5%
3.32E-03
AM-241
85.31
1.76E-03
AM-241
87.9%
7.05E-04
AM-241
79.9%
1.53E-04
AH-243
51.0%
1.32E-05
AM-243
98.7%
6.65E-07
AM-243
100,0%
100.00
2.05E-03
AM-241
73.31
1.98E-03
AM-241
74.3%
1.80E-03
AM-241
76.9Z
1.56E-03
AM-241
80. 5%
1.20E-03
AM-241
85. 3Z
6.37E-04
AH-241
87.9%
2.55E-04
AM-241
79.9%
5.54E-05
AM-243
51. OZ
4.80E-06
AM-243
98. 7%
2.41E-07
AH-243
100.0%
200.00
7.35E-Q4
AM-241
73,3%
7.11E-04
AH-241
74.3Z
6.46E-04
AM-241
76. 9Z
5.S8E-04
AM-241
80.5%
4.30E-04
AM-241
85.3%
2.28E-04
AM-241
87.9%
9.15E-05
AM-241
79.9%
1.98E-05
AM-243
51.0%
1. 721-06
AM-243
98.71
8.62E-08
AM-243
100. OZ
500.00
1.84E-04
AH-241
73. 3%
1.7SE-04
AM-241
74. 3%
1.62B-04
AM-241
76.9%
1.40E-04
AM-241
80.5%
1.08E-04
AM-241
85.3%
5.70E-05
AM-241
87.9%
2.29E-05
AH-241
79. 9%
4.96E-06
AM-243
51.0%
4.29E-07
AM-243
98. 7Z
2.16E-08
AM-243
100. 01
750.00
9.80E-05
.\M-24l
73.3%
9.49E-05
AH-241
74.3%
8.62E-05
AM-241
76.9%
7.44E-05
AM-241
80. 5%
5.74E-05
AM-241
85.3%
3.04E-05
AM-241
87.9%
1.22E-05
AM-241
79.9%
2.65E-06
AM-243
51.0%
2.29E-07
AH-243
98.7%
1.15E-08
AM-243
100.0%
1000.00
6.23E-05
AH-241
73. 3Z
6.03E-05
AH-241
74.3%
5.48S-05
AM-241
76.9%
4.731-05
AM-241
80.5%
3.65E-05
AM-241
85.3%
1.93E-05
AM-241
87.9%
7.761-06
AH-241
79.9%
1.68E-06
AM-243
51.0%
1.46E-07
AM-243
98. 7%
7.32E-09
AM-243
100.0%
1500.00
3.25E-05
AH-241
73.3%
3.14E-05
AM-241
74.3%
2.86E-05
AH-241
76.9%
2.47E-05
AM-241
80-. 5%
U90E-05
AM-241
85.3%
1.01E-05
AM-241
87.9%
4.04E-06
AM-241
79.9%
8.77E-07
AM-243
51.0Z
7.59E-08
AM-243
98.7%
3.81E-09
AM-243
100.0%
2000.00
2.02E-05
AH-241
73.3%
1.96E-05
AH-241
74.3%
1.78B-05
AM-241
76.9Z
1.54E-05
AM-241
80.5%
1.19E-05
AM-241
85.3%
6.28E-06
AM-241
87.9%
2.S2E-06
AH-241
79.9%
5.46E-07
AH-243
51.0%
4.73E-08
AM-243
98.7%
2.38E-09
AM-243
100.0%
4000.00
6.16E-06
AH-241
73.3%
5.96E-06
AH-241
74.3%
5.42E-06
AH-241
76.9Z
4.68E-06
AM-241
80.5%
3.61E-06
AH-241
85.3%
1.9 IE-OS
AM-241
87.9%
7.67E-07
AH-241
79.9%
1.66E-07
AM-243
51.0%
1.44E-08
AM-243
98.7%
7.23E-10
AH-243
100.0%
-------
6.4.1 All retardation factors equal one
Release to the aquifer due to drilling: Direct hiton waste
Tables 6.41 and 6.47 give the annual dose rates and contaminated
areas, respectively, for a direct hit, drilling release to the aquifer
because of drilling into the granite repository when the retardation
factors are all equal to one. The annual dose rates can be compared to
those in Table 5.7. The annual dose rates, until 500 years, are a
factor of about 1,000,000 times larger than those of the base case,
primarily because 'Am-241 moves 20 meters in only 10 years rather than
1000. The peak dose rate of 2660 rem/yr, 98.2% from Am-241, occurs at
10 years, 20 meters. The nuclides and their accompanying high dose
rates quickly spread through the aquifer. Later, dose rates near the
borehole (e.g., 20 meters at 1000 years) are slightly lower than those
of the base case (e.g., 570 rem/yr instead of 630 rem/yr at 1000 years
and 20 meters) because the nuclides have flowed beyond the distance
considered. In the expression describing the release (equation 4.4) we
have the term "exp(x. kx/v)", k is now much smaller, so this term
has a visible, although smaller, influence on the results.
The effect of low retardation factors is best seen by comparing
Table 6.47 with Table 5.11. Table 6.47 shows that much larger areas
are contaminated very badly at early times, and also that the spread of
contamination at later times is greater by two to three orders of
magnitude. The contaminated areas over 0.5 rem/yr increase steadily
until 2000 years, when the entire length of aquifer studied has been
contaminated. After 2000 years, radiological decay and flow of the
nuclides cause the area of contamination to drop.
Release to the aquifer due to drilling: Granite tank
Table 6.44 gives the annual dose rates for a release to the aquifer
because of drilling into the granite tank when all the retardation
factors equal one. The highest dose rate, 14,000 rem/yr, occurs at the
earliest time and closest point, ten years and 20 meters, because all
nuclides reach this distance within ten years. Am-241 is uie maximum
172
-------
contributor until about 2000 years, then Am-243 becomes dominant. The
dose rate decreases steadily with both time and distance. Table 6.47
shows that the contaminated areas reach a maximum of 360 ha 2000 years
after the event. The areas increase rapidly as the nuclides spread,
reach a maximum value, then shrink as the nuclides decay. This is the
only drilling event that has any contaminated areas that would give
more than 5000 rem/yr for the first 500 years after the event.
Release to the aquifer due to drilling: Brine pocket
Table 6.43 gives the annual dose rates from drinking aquifer water
after drilling into a brine pocket 1000 years after the repository was
sealed and all retardation factors equal to one. The annual dose rates
in Table 6.43 are slightly less than twice those of Table 6.41,
reflecting the fact that the brine pocket is in contact with waste from
two canisters. The maximum dose rate is 4800 rem/yr, almost all from
Am-241, 10 years after the event at a distance of 20 meters. Am-241
dominates until after 2000 years, then decays and Am-243 dominates to
10,000 years.
Table 6.47 shows the areas contaminated above specific dose rate
levels. The contamination spreads very quickly. The discussion in the
direct hit scenario of this section applies here also. The area
contaminated above 0.5 rem/yr increases from 0.18 ha after 10 years to
330 ha at 1000 years. At and beyond 2000 years, the contaminated areas
shrink, mostly as a result of the decay of americium isotopes.
Release to the aquifer due to faulting: Direct hit on waste
Table 6.42 gives the annual dose rates for a faulting event that
hits a row of waste canisters when the retardation factor for all
nuclides is one. The peak dose rate, 8500 rem/year, almost all from
Am-241, first occurs about 200 years after the event at 500 m. After
about 2000 years, the Am-241 has decayed to lower levels and Am-243
173
-------
dominates until 10,000 years. Since all of the nuclides are moving at
the same velocity in the aquifer, the percentage at each location is
the same,
Table 5.22 presents the annual dose rates for comparison to
Table 6.42. The annual dose rates of Table 5.22 are roughly the same
over the entire length of the repository at any time up to 1000 years.
This is because each point is affected only by the nearest 20 meters.
In Table 6.42, the doses at 1000 years vary by a little over a factor
of ten. Dose rates throughout are much higher when the retardation
factors equal one.
Release to the aquiferdueto faulting: Granite tank
Table 6.45 presents the annual dose rates from a fault line inter-
secting a tank of contaminated repository water in granite. Five per-
cent of the inventory has leached into the tank before the faulting
event except for solubility-limited nuclides. Doses rates are very
large because of the large tank inventory and the rapid movement of
nuclides. The highest dose rate, 12 million rem/yr, is almost all from
Am-241. Am-241 dominates until about 2000 years, then Am-243 at
5,000 years, and Pu-239 at 10,000 years.
Release to jthe aqjiiifer due to shaft seal leakage
Table 6.46 shows the annual dose rates that result from the
degradation of the plugged shaft seal. This is modeled similarly to
the drilling event, hence the results are similar. The shaft has a
? ?
cross-sectional area of 25 m , vs 0.1 m for a borehole, this allows
for higher flow and dose rates. The maximum dose rate is 30,000 rem/yr
at 1000 years and 20 meters. Am-241 dominates to about 2000 years
after the event, then it decays enough so that Am-243 is dominant to
about 10,000 years. Although the shafts begin to deteriorate imme-
diately after sealing, no nuclides are released until the canisters
fail at 500 years.
174
-------
Table 6.41
Dose Equivalent Rates (rem/yl) from Drinking Grounduater Contaminated by Hadionuetides
Released by Borehole Drilling
1030 Years After Repository Sealing
Drill Hits Haste
All Retardation Factors Equal One
DISTANCE (meters)
TCg (yr)
l.OOE+Oi
2.00S+01
5.QOE+01
l.OQE+02
2.QOE+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
20.00
2.66B+03
AM-241
98.21
2.62E+03
AM-241
98.22
2.50E+03
AM-241
98. 1Z
2.31E+03
AM-241
98.0%
1.97E+03
AH-241
97.7*
1.23E+03
AH-241
96. 5Z
i
5.68E+02
AM-241
93. 1%
1.38E+Q2
AM-241
76. 61
1.91E+01
AM-243
95. 4Z
7.05E+00
AM-243
99.4%
50.00
0.0
NONE
0.0%
0.0
HONE
0.02
1.58E+03
AM-241
98. IX
1.46E+03
AM-241
98. OK
1.25E+03
AM-241
97. 7X
7.78E+02
AM-241
96, SZ
3.60E+02
AM-241
93. U
8.72S+01
AM-241
76.6%
1.21E+01
AM-243
95. 4Z
4.46E+00
AM-243
99.4%
100.00
0.0
SOME
o.oz
0.0
HOHS
o.oz
1.12E-M33
AM-241
93. 1Z
1.04E+03
AH-241
98.0Z
8.84E+02
AM-241
97.7%
5.52E+02
AM-241
96, 5Z
2.551+02
AM-241
93.11
6.18E+Q1
AM-241
76. 6%
8.56E+OQ
AM-243
95.4%
3.16B-H>0
AM-243
99.4%
200.00
0.0
HOME
o.oz
0.0
NONE
O.OZ
0.0
NONE
O.OZ
7.36E+Q2
AM-241
98. OZ
6.28E+02
AM-241
97,7%
3.92E+02
AM-241
96.5%
1.81E+02
AM-241
93.1%
4.39E+01
AM-241
76.6%
6.08E+00
AM-243
95.4%
2.25E*QO
AK-243
99. 4Z
500.00
0.0
NONE
0.0%
0,0
HONE
0.0%
0.0
RONS
O.OZ
0.0
HOHS
0.0%
0.0
HONE
O.OZ
2.51E+02
AM-241
96. 5Z
1.16E+02
AM-241
93. IX
2,821+01
AM-241
76.6%
3.90E+00
AM-243
95.4Z
1.44E+00
AM-243
99.5%
750.00
0.0
NONE
O.OZ
0,0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
2.08E+02
AM-241
96. 5Z
9.61E+01
AM-241
93.1%
2.33E+01
AH-241
76. 6Z
3.22E+00
AM-243
95.4Z
1.19E+00
AM-243
99. 5%
1000.00
0.0
HONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0,0
NONE
O.OZ
0,0
NONE
O.OZ
1.82E+02
AM-241
96.5%
8.42E+01
AM-241
93.1%
2.04E+01
AM-241
76.6%
2.82E+00
AM-243
95.4%
1.04E+00
AM-243
99. 5Z
1500,00
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
HOHE
O.OX
0.0
NONE
0,0%
0,0
NONE
0.0%
0.0
HONE
0.0%
7.04E+Q1
AM-241
93. 1Z
1.71E+01
AM-241
76.61
2.36E+00
AM-243
95.4%
8.73E-01
AM-243
99.5%
2000.00
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
0.0%
0.0
N03E
O.OZ
0.0
HONE
0,0%
6.25E+01
AM-241
93. 1Z
1.51E+01
AM-241
76. 6Z
2.09E+00
AM-243
95. 4%
7.741-01
AM-243
99.5%
4000.00
0.0
NONE
0.0%
O.C
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HOHE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.0%
1.18E+01
AM-241
76.6%
1.63E+00
AM-243
95.4Z
6.02E-01
AM-243
99. 6%
-------
table 6.42
TIME (yr)
1.00E+Q1
2.00E+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
Dose Equivalent Rates (rem/yr) from Drinking Grounduatec Contaminated by Radicmnclides
Heleaaea by Borehole Drilling in GRANITE
1000 Years After Repository Sealing
Drill Hits Repository Hater
All Retardation Factors Equal One
DISTANCE (meters)
20.00
1.45E+Q4
AM-241
98.2%
1.45E+Q4
AM-241
98. 21
1.461+04
AM-241
98. 1Z
1.45E+04
AM-241
98.0Z
1,411+04
AM-241
97,71
1. 19E+04
AM-241
96.55!
7.73E+03
AM-241
93. IX
2.90E+03
AM-241
76.61
8.50E+02
AM-243
95.5%
7.08E+02
AB-243
99.91
50.00
0.0
NONE
o.oz
0.0
HONE
O.OZ
3.01B+03
AM-241
98. 1%
8.99E+03
AH-241
98.01
8.79S*03
AM-241
97.7%
7.45E+03
AH-241
96. 5Z
4.86E+03
AM-241
93. 1Z
1.83E+03
AH-241
76. 6Z
5.37E-HJ2
AM-243
95.5%
4.47E+02
AM-243
99.9%
100.00
0.0
NONE
O.OZ
0.0
NONE
0.0%
6.14E+03
AM-241
98.11
6.1SE+03
AH-241
98.0%
6.05E+03
AM-241
97.71
5.17E+03
AM-241
96.5%
3.40B+03
AM-241
93.1%
U29E+03
AM-241
76. 6Z
3.79E+02
AM-243
95.5%
3.16E+02
AH-243
99.9%
200.00
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
O.OZ
4.04E+03
AM-241
98.0%
4.03E+03
AM-241
97.7%
3.52E+03
AM-241
96.5%
2.35E+03
AM-241
93.1%
B.98E+02
AM-241
76. 6%
2.66E+02
AM-243
95.5%
2.23B+02
AM-243
99.9%
500.00
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NOME
O.OZ
0.0
NONE
O.OZ
1.96E*03
AM-241
96. 5%
1.38E+03
AM-241
93.1%
5.46E+02
AM-241
76. 6Z
1.66E+02
AH-243
95.5%
1.40E+02
AH-243
99. 9Z
750.00
0.0
NOME
O.OZ
0.0
NONE
0.02
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
0.0%
1.40E+03
AM-241
96.5%
1.05E+03
AM-241
93.1%
4.31E+02
AM-241
76. 6%
1.34E+02
AM-243
95.5%
1.14E+02
AM-243
99. 9Z
1000.00
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
HOME
O.OZ
1.03E+03
AM-241
96.5%
8.39E+02
AM-241
93.1%
3.60E+02
AH-241
76. 6%
1.15E+02
AM-243
95.5%
9.80E+01
AM-243
99.9%
1500.00
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0,0
NONE
O.OZ
0.0
NONE
0.0%
5.63E+02
AM-241
93.1%
2.70E+02
AM-241
76. 6Z
9.13E+01
AM-243
95.5%
7.91E+01
AM-243
99.9%
2000.00
0.0
HOHS
O.OZ
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
o.oz
0.0
HOME
O.OX
3.68E+02
AM-241
93. 1Z
2.12E+02
AM-241
76. 6Z
7.70E+01
AM-243
95. 5%
6.78E+01
AM-243
99. 9Z
4000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
7.45E+01
AM-241
76. 6Z
4.7BE+01
AM-243
95.5%
4.56E+01
AM-243
99. 9Z
-------
Table 6.43
Dose Equivalent Rates (ren/yr) froa Drinking Groundwater Contaminated by Radionuclidea
Released by Borehole Drilling in BEDDED SALT
1000 Years After Repository Sealing
Brill Hits Repository Hater
All Retardation Factors Equal One
DISTANCE (metera)
TIKE (yr)
l.OOE+Ol
2.00E+01
5,001+01
l.QOE+02
2.00E+02
5.00E+02
1.00E+03
2.00E+03
5.00E+03
l.OOE+04
20,00
4.841*03
AH-241
98.21
4.80E+03
AM-241
98.21
4.58E+03
AM-241
9S.1Z
4.231+03
AB-241
98. 0%
3.61B+03
AM-241
97.7%
2.251+03
AM-241
96, 5Z
1.C4E+03
AH-241
93. IX
2.54E+02
AM-241
76. 61
3.46S+01
AM-243
95.41
1.28E+01
AM-243
99.6%
50,00
0.0
HONE
0.0%
0.0
HOME
o.oz
2.9QE+03
AM-241
98.12
2.68E+03
AM-241
98.0%
2.28E+03
AH-241
97.71
1.43E+03
AH-241
96. 5Z
6.60E+02
AM-241
93. U
1.61E+Q2
AH-241
76.61
2.20E+01
AH- 243
95.4%
8.11E+00
AM-243
99. 6Z
100.00
0.0
HONE
O.OZ
0.0
HONE
o.ox
2.05E+03
AM-241
98. U
1.90E+03
AM-241
98.02
1.62E+03
AH-241
97,71
1.01E+03
AM-241
96. 5Z
4.68E+02
AM-241
93. 1Z
1. 14E+02
AM-241
76. 6Z
1. 561+01
AM-243
95. 4Z
5.78E+00
AM-243
99.6%
200.00
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
HONE
O.OZ
1.35B+03
AM-241
98.0Z
1.15E+03
AH-241
97. 7Z
7.18E+02
AM-241
96.5%
3.32E-HJ2
AM-241
93. 1Z
8.09E+01
AM-241
76. 6Z
1.11E+01
AM-243
95.4%
4.07E+00
AM-243
99. 6Z
500.00
0,0
HONE
O.OZ
0.0
HONK
O.OZ
0.0
HONE
O.OZ
0.0
mm
o.ox
0.0
HONE
O.OX
4.61E+02
AM-241
96. 5Z
2.13E+02
AH-241
93. 1Z
5.14E+01
AH-241
76. 6Z
7.11B+00
AM-243
95.4Z
2.63E+00
AH-243
99. 6Z
750.00
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
3.811+02
AM-241
96. 5X
1.76E+02
AM-241
93. 1Z
4.26E+01
AM-241
76. 6%
5.82B+00
AM-243
95.4Z
2.16E+00
AM-243
99.61
1000,00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
3.34E+02
AM-241
96. 5Z
1.54E+02
AM-241
93, U
3. 73t>01
AM-241
76. 6Z
5.15E+00
AM-243
95.4%
1.90E4-00
AM-243
99. 7Z
1500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
1.29B+02
AM-241
93. 1Z
3.13E+01
AH-241
76. 6Z
4.29E+00
AM-243
95.5%
1.58E+00
AH-243
99. 7Z
2000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
1.15E+02
AM-241
93,1%
2.78E+01
AM-241
76. 6X
3.80E+00
AM-243
95.5%
1.40E+00
AM-243
99. 7Z
4000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0,0
NONE
O.OX
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
2.16E+01
AH-241
76. 6Z
2.98E+00
AH-243
95. 5%
I.IOE+OO
AM-243
99. 7Z
-------
CD
Table 6.44
Doae Equivalent Ratea (reta/yr) from Drinking Groundwater Contaminated by Radionuclidea
Released by fault Movement
1000 Years After RepOBitory Sealing
Haste Directly Affected
All Retardation Factors Equal One
PISTANCE (metera)
lim (yr)
l.OQE+01
2.0QE+01
5.00E+01
l.OOE+02
2.00E+02
5.0QB+02
l.OQE+03
2.00E+03
5.00E+03
l.OOE+04
SO.OO
2.Q8B+Q3
AM-241
97, 6Z
2.04E+03
AH-241
97.5%
1.9SE+03
AM-241
97.4%
1.80E+03
AM-241
97. 2%
1.54E+03
AM-241
96.8%
9.67E+02
AM-241
95. 1%
4.55E+OZ
AM-241
90.31
1.21E+02
AM-241
67,7%
2.87E+01
AH-243
49. U
1.33E+01
AM-243
41.01
50.00
2.14E+03
AH-241
97.61
3.23E+03
AM-241
97.5%
3.41E+03
AM-241
97.4%
3.15E+03
AM-241
97.21
2.7QE+03
AM-241
96.8% .
1.69E+Q3
AM-241
95.11
7.95E+02
AM-241
90.3%
2.11E+02
AM-241
67. n
5.02E+01
AM-243
49. U
2.32E+01
AM-243
41,0%
100.00
2.14E+Q3
AM-241
97. 6X
3.23E*03
AH-241
97. 5*
5.05E+03
AM-241
97.4Z
4.67E+03
AM-241
97.2%
3.991+03
AM-241
96.8%
2.50B+03
AM-241
95.1%
1.18E+03
AM-241
90.3%
3.13E+02
AM-241
67.7%
7.44B+01
AM-243
49.1%
3.43E+01
AM-243
41.0%
200.00
2.14E+03
AH-241
97.6%
3.23E+03
AM-241
97.5%
5.19E+03
AM-241
97.4%
6.79E+03
AH-241
97.2%
5.80E+03
AM-241
96.8%
3.64E+03
AM-241
95.1%
1.711+03
AM-241
90.3%
4.55E+02
AM-241
67.7%
1.08E+02
AM-243
49.1%
4.99E+01
AM-243
41.0%
500.00
2.14E+03
AM-241
97.6%
3.23E+03
AM-241
97.5%
5.19S+03
AM-241
97.4%
6.97E+03
AM-241
97.2%
8.58E+03
AM-241
96.8%
5.89E+03
AM-241
95.1%
2.77E+03
AM-241
90.3%
7.36E+02
AM-241
67.7%
1.75E+02
AM-243
49.0%
8.08E+01
AM-243
41.0%
750.00
2.14E+03
AH-241
97.6%
3.23E+03
AM-241
97.5%
5.19S+03
AM-241
97.4%
6.97E+03
AM-241
97.2%
8.581+03
AM-241
96.8%
7.2SE+03
AH-241
95.1%
3.411+03
AM-241
90.3%
9.06E+02
AH-241
67.7%
2.16E+02
AM-243
49.0%
9.96E+01
AH-243
40.9%
1000.00
2.14E+03
AM-241
97.6%
3.23E+03
AM-241
97.5%
5.19B+03
AH-241
97.4%
6.97E+03
AM-241
97.2%
8.58E+03
AM-241
96.8%
8.38E+03
AH-241
95.1%
3.94E+03
AM-241
90.3%
1.05E+03
AM-241
67.7%
2.49E+02
AM-243
49.0%
1.15E+02
AM-243
40.9%
1500.00
2.14E+03
AM-241
97.6%
3.23E+03
AH-241
97.5%
5.19S+03
AM-241
97.4%
6.97E+03
AM-241
97.2%
8.58E+03
AM-241
96.8%
8.58E+03
AM-241
95.1%
4.81E+03
AM-241
90.3%
1.28E+03
AM-241
67.7%
3.05E+02
AM-243
49.0%
1.411+02
AM-243
40.9%
2000.00
2.14E+03
AM-241
97.6%
3.23E+03
AM-241
97,5%
5.19S+03
AM-241
97.4%
6. 978+03
AH-241
97.2%
8.58E+03
AM-241
96.8%
8.58E+03
AM-241
95.1%
5.531+03
AM-241
90.3%
1.47E+03
AM-241
67.7%
3.50E+02
AM-243
48.9%
1.62S+02
AM-243
40,8%
4000.00
2.14E+03
AU-241
97.6%
3.23E+03
AM-241
97.5%
5.19E+03
AH-241
97.4%
6.97E+03
AM-241
97.2%
8.58E+03
AM-241
96.8%
8.58E+03
AM-241
95.1%
5.67E+03
AM-241
90.3%
2.03E+03
AM-241
67.6%
4.85E+02
AM-243
48,8%
2.25E+02
AM-243
40.6%
-------
Table 6,45
TIME(yr)
l.OOE+01
2.00E+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OQE+03
2.00E+03
5.QOE+03
l.OOE+04
Dose Equivalent Rates (rem/yr) (TOD Drinking Groundwster Contaminated by Radionuclides
Released by Fault Movement in GRANITE
1000 tears After Repository Sealing
Repository Mater Affected
All Retardation Factors Equal One
DISTANCE (meters)
20.00
1. 16E+0?
AM-241
95. 7%
2.0QE+Q6
AM-241
95,6%
3.05E+05
AM-241
95,4%
2.77E+05
AM-241
95. IX
2.18E+05
AM-241
94.4%
1.51E+05
AM-241
91.6%
7.34E+04
AM-241
84.21
2.21E+04
AH-241
55.8%
5.90E+03
AM-243
36.0%
2.50E+03
PU-239
36.8%
50,00
1.26E+07
AM-241
95, 7%
9.35E+06
AM-241
95.6%
5.78E+OS
AM-241
95.4%
4.85E+05
AM-241
95.1%
4.16E+05
AM-241
94.4%
2.64E+05
AH-241
91.6%
1.28E+05
AM-241
84.2%
3.86E+04
AM-241
55.8%
I.Q3E+04
AM-243
36.0X
4.38E+03
PU-239
36.8%
100.00
1.268+07
AM-241
95.7%
9.3SE+06
AM-241
95,61
3.94E+06
AM-241
95.4%
7.20E+05
AM-241
95.1%
6.18E+05
AM-241
94,4%
3.92E+05
AM-241
91.6%
1.91E+05
AH-241
84. 2S
5.73E+04
AM-241
55.8%
1.53E+04
AM-243
36.0S
6.50E+03
PU-239
36.8%
200,00
1.26E+07
AM-241
95.71
9.35E+06
AM-241
95.6%
5.59E+06
AM-241
95.4%
2.32E+06
AM-241
95.1%
9.01E+05
AM-241
94.4%
5.72E+05
AM-241
91.6%
2.78E+05
AM-241
84.2%
8.35E+04
AM-241
55. 81
2.23E+04
AH-243
36.0%
9.47E+03
PU-239
36.8%
500.00
1.261+07
AM-241
95.71
9.35E+G6
AM-241
95.6%
5.59E+06
AM-241
95. 4X
4.13E+06
AM-241
95.1%
3.18E+06
AM-241
94.4%
9.34E+05
AM-241
91.6%
4.54E+05
AH-241
84.2%
1.36E+05
AM-241
55.8%
3.65E+04
AM-243
35.9%
1.55E+04
PU-239
36.8%
750,00
1.26E+07
AM-241
95.7%
9.35E+06
AH-241
95.6X
5.59E+06
AM-241
95.4%
4.13E+06
AM-241
95.1%
3.188+06
AM-241
94.4%
1. 16E+06
AK-241
91.6%
5.64E+05
AH-241
84.2%
1.69E+05
AM-241
55.8%
4.53E+04
AM-243
36.0%
1.92E+04
PU-239
36.8%
1000.00
1.26E+07
AM-241
95.7%
9.35E+06
AM-241
95.6%
5.59E+06
AM-241
95.4%
4.13E+06
AM-241
95.1%
3.18E+06
AM-241
94.4%
1.36E+06
AM-241
91.6%
6.56E+05
AM-241
84.2%
1.97E+05
AM-241
55.8%
5.28E+04
AM-243
36.0%
2.24E+04
PU-239
36.8%
1500.00
1.26E+07
AM-241
95.7%
9.351+06
AM-241
95. 6Z
5.59E+06
AM-241
95,4%
4.13E+06
AM-241
95.1%
3.18E+06
AM-241
94.4%
2.14E+06
AM-241
91.6%
B.14E+05
AM-241
84.2%
2.45E+05
AM-241
55.9%
6.55E+04
AM-243
35.9%
2.78E+04
PU-239
36.8%
2000.00
1.26E+07
AM-241
95.71
9.35E+06
AM-241
95.6%
5.59E+06
AM-241
95.4%
4.13B+06
AM-241
95.1%
3.18E+06
AM-241
94.4%
2.14E+06
AM-241
91.6%
9.53E+05
AM-241
84.2%
2.86E+05
AH-241
55.8%
7.65E+04
AM-243
35.9%
3.24E+04
PU-239
36.8%
4000.00
1.26E+07
AM-241
95.71
9.35E+06
AM-241
95.6%
5.59E+06
AM-241
95.4%
4.13E+06
AM-241
95.15
3.18E+06
AM-241
94.4%
2.14E+06
AM-241
91.6%
1.25E+06
AM-241
84.2%
4.21E+05
AM-241
55.8%
1. 13E+05
AM-243
36.0%
4.7SE+04
PU-239
36.8%
-------
table 6.46
00
o
Dose Equivalent Rite* (reta/yr) from Drinking Groundwater Contaminated by Radionuclides
Released by Shaft Seal Leakage in GRANITE
All Retardation Factors Equal One
DISTANCE (aetera)
IDC (yr)
l.OOE+Ql
2.00E+01
5.00S+01
l.OQE+02
2.00E+02
5.00E+02
l.QQB+03
2.00E+03
5.00E+03
l.OOE+04
20.00
9.61E-Q1
AM-241
98,9%
4.04E+01
AM-241
99. OX
3.6ZE+02
AM-241
99.0%
1.46E+03
AM-241
99.0Z
5.01E+03
AM-241
98.8%
1.81E+04
AH-241
98.31
2.98S+04
AM-241
96.5Z
2.36E+04
AM-241
87.01
1.112+04
AM-243
91.4Z
1.81E+04
A»-243
99.91
50.00
0.0
NONE
O.OZ
0.0
RIME
O.OZ
1.07S+02
AH-241
99.0%
6.701+02
AM-241
99.0Z
2.74E+03
AM-241
98.81
1.09E+04
AH-241
98.31
1.84E+04
AH-241
96,51
U48K+04
AM-241
87. OZ
6.96B+03
AM-243
91.4Z
1. 14E+04
AK-243
99.9%
100.00
0.0
NONE
O.OZ
0.0
HOME
O.OZ
2.39E+00
AM-241
99.02
2.39E+02
AM-241
99.0Z
1.48E+03
AM-241
98.8Z
7.01E+03
AM-241
98.3*
1.24E+04
AM-241
96.51
1.02E+04
AM-241
87.02
4.89E+03
AM-243
91.4Z
8.05E+03
AM-243
99. 9Z
200.00
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
HONE
O.OZ
3.73E+00
AM-241
98.91
5.20E+02
AM-241
9B.8Z
4.06K+03
AM-241
98.3Z
8.06E+03
AM-241
96. 5Z
6.94E+03
AH-241
87.01
3.40E+03
AM-243
91.4Z
5.65E+03
AM-243
99. 9Z
500.00
0.0
NONE
O.OZ
0.0
DOME
O.OZ
0.0
HONE
0,0%
0.0
NOME
O.OZ
0.0
NONE
O.OZ
1.16B+03
AM-241
98.3%
3.78B+03
AM-241
96. 5Z
3.86E+03
AM-241
87 .OX
2.06E+03
AM-243
91.4%
3.50E+03
AM-243
99.9%
750.00
0.0
NONE
0.0%
0.0
NODS
O.OZ
0.0
NONE
0.0%
0.0
HONE
O.OZ
0.0
HONE
O.OZ
3.06E+02
AM-241
98.3%
2.29E+03
AM-241
96. 5Z
2.80E+03
AM-241
87.0%
1.62E+03
AM-243
91.4%
2.81E+03
AM-243
99, 9Z
1000.00
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
1.04E+01
AM-241
98.2Z
1.38E+03
AM-241
96.5%
2.14E+03
AM-241
87.0Z
1.35E+03
AM-243
91.4%
2.39E+03
AH-243
99. 9Z
1500.00
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
MORE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NOME
0.0%
3.74E+02
AM-241
96.5%
1.31E+03
AM-241
87.0%
1.01E+03
AM-243
91. 4Z
1.88E+03
AM-243
99. 9%
2000.00
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.0%
1.181+01
AM-241
96.5%
8.02E+02
AM-241
87.0%
8.01E+02
AM-243
91.4%
1.57E+03
AM-243
99.9%
4000.00
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
HONE
0.0%
0.0
NONE
0.0%
0.0
HONE
o.ez
0.0
NONE
0.0%
0.0
NONE
0.0%
7.27E+00
AM-241
86.91
3. 72E+02
AM-243
91.4%
9.39E+02
AM-243
99.9%
-------
Table 6.47
Area (ha*) of the Aquifer Contaminated
Above the Specified Dose Rate Levels
By Drilling 1000 Years after Sealing
Low retardation factors
Event Length
Description after
Direct hit on
the waste
Drill hits
brine pocket
Drill hits
granite tank
Shaft seal
leakage beginning
500 years
after closing
of time
event (yr)
10-20
50
100
200
500
1000
2000
5000
10000
10-20
50
100
200
500
1000
2000
5000
10000
10-20
50
100
200
500
1000
2000
5000
10000
10-20
50
100
200
500
1000
2000
5000
10000
Dose Rate Levels (rem/yr)
0.5
0.17
1.83
5.05
4.79
51.1
132
303
196
104
0.18
1.90
5.24
53.5
139
329
234
166
2.26
0.18
1.94
5.39
5.37
55.9
148
363
298
221
0.18
1.91
5.29
5.24
54.1
141
332
222
172
5
0.15
1.54
4.21
4.15
40.5
97.6
172
2.17
0.07
0.15
1.62
4.45
43,6
108
215
12.0
0.60
0
0.16
1.68
4.62
4.60
46.5
119
263
164
2.84
0.16
1.64
4.50
4.44
44.2
110
219
6.04
0.75
50
0.12
1.19
3.17
3.08
25.9
40.3
0.67
0
0
0.12
1.29
3.47
30.4
61.2
4.11
0
0
0
0.13
1.36
3.69
3.67
34.4
79.2
81.9
0.48
0
0.13
1.32
3.54
3.47
31.4
64.6
5.09
0
0
500
0.08
0.68
1.50
1.20
0.53
0.04
0
0
0
0.09
0.84
2.08
2.72
0.25
0
0
0
0
0.09
0.95
2.42
2.39
13.5
5.3
0.17
0
0
0.09
0.88
2.19
2.07
4.54
0.47
0
0
0
5000
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0.04
0.08
0.07
0.07
0.02
0
0
0
0
0.02
0.03
0
0
0
0
0
0
0
*1 hectare (ha) = 10^ square meters
181
-------
With a retardation factor of 1, the nuclides spread, rapidly
throughout the aquifer. Table 6.47 shows that the largest contaminated
area occurs at 2000 years, 330 ha for dose rates above 0.5 rem/yr,
6.4.2 Higher retardation factors
All of the events with high retardation factors (Tables 6.48
through 6.52) can be discussed in one section because all of the annual
dose rates are very small. The americium isotopes which have dominated
most of the previous cases, are now held back by the chemical sorption
properties of the aquifer strata, taking about 100,000 years to move
20 meters. By this time, Am-243 has decayed very substantially. 1-129
and carbon-14 (C-14), with retardation factors equal to one, are the
dominant nuclides in drilling releases and remain so for about
1000 years. Np-237 is the dominant isotope later on in Tables 6.51 and
6.52, faulting to aquifers. Pu-239 travels the one-meter distance used
as the lower bound for integration in 10,000 years, and produces a
highest dose rate of 850 rem/yr, 10,000 years after the faulting event
(Table 6.52). Sn-126 and Cs-135 appear in Table 6.49 in the brine
pocket release to the aquifer. The shaft seal releases are not listed,
they are essentially the same as the drilling hit releases (Table 6.48).
Only tank releases as a result of faulting produce dose rates over
100 rem/yr.
Generally speaking, nuclides with low retardation factors are the
most important. 1-129, C-14, and Np-237 are the dominant nuclides,
with very low annual dose rates, for all the drilling events
(Tables 6.48, 6.49, and 6.50).
6.5 Effect of d Better-Sealed Borehole
In these scenarios, we assigned the borehole seal an initial
permeability of 0.315 m/yr (10 cm/s) when it was resealed and
postulated that the permeability degraded at a rate of
3.15 x 10"4 m/yr2 (10~9 cm/s2) for a period of 10,000 years.
The permeability at any time t is equal to:
0.315 + (3.15 x 10"4 t).
182
-------
table 6.48
CD
CO
TIME (yr)
l.OOE+Ol
2.00E+01
5.00E+01
l.OOE+02
2.001+02
5.00E+02
l.OQE+03
2.00E-IO3
5.00E+03
l.OOE+04
Do«e Equivalent late* (rca/yr) from Drinking Croundwater Contaminated by Radionuelidct
Released by Borehole Drilling
1000 Year* After Repository Staling
Drill Hiti W«at*
High Retardation Factor*
DISTANCE (mettra)
20.00
2.33E-05
I -129
71.2Z
2.33E-05
I -129
71.3%
2.31E-05
I -129
71.4Z
8.06E-04
C - 14
97. 2Z
7.8IE-04
C - 14
97. 1Z
7.39E-04
0-14
97. U
5.26E-03
NP-237
87.41
4.22E-03
OT-237
87,41
3.09E-03
MF-237
91.02
3.61E-03
HP-237
67.0%
50.00
0.0
HONE
0.0%
0.0
NONE
0.0%
1.47E-05
I -129
71.4Z
1.46E-05
I -129
71.6%
1.43E-05
I -129
72.01
4.74E-04
0-14
97. 1Z
4.25E-04
G - 14
97.01
3.42E-04
C - 14
96.6Z
2.14E-03
HP-237
91. 6Z
1.63E-03
HP-237
96.2%
100.00
0.0
HONK
O.OZ
0.0
NONE
0.0%
1.04B-05
I -129
71.3Z
1.03E-05
I -129
71.5%
1.02B-05
I -129
71.9%
3.43E-04
0 - 14
97. 2Z
3.07E-04
C - 14
97.01
2.47E-04
C - 14
96. 7Z
2.07B-03
HP-23?
93.81
1.23E-03
HP-237
96. 3X
200.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
7.36E-06
I -129
71. 3Z
7.24E-06
I -129
71.7Z
6.93E-06
I -129
72. 7Z
2.28E-04
C - 14
97. 1Z
1.83E-04
C - 14
96.8%
9.58E-05
C - 14
95. 4Z
1.33E-03
NP-237
97. 5Z
500.00
0.0
KIKE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
4.47E-06
1 -129
72 .3Z
4. 19E-06
I -129
73. 5Z
3.75E-06
I -129
74. 3Z
6.95B-05
C - 14
95.9Z
2.40E-05
C - 14
91. 9Z
750.00
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
3.72E-06
I -129
71.9Z
3.47E-06
I -129
73. 3Z
3.10E-06
1 -129
74. 3Z
6.37E-05
C - 14
96.3Z
2.19E-05
C - 14
92. 7Z
1000.00
0.0
NONE
O.OZ
0.0
mm
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
3.28E-06
I -129
71. 4Z
3.05E-06
I -129
73. OZ
2.71E-06
I -129
74. 2Z
6.19E-05
C - 14
96.7%
2.12E-05
C - 14
93. 4Z
1500.00
0.0
NONE
O.OZ
0.0
HOME
O.OZ
0.0
NODE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
2.57E-06
1 -129
72.4Z
2.27E-06
I -129
74. 1Z
1.71E-06
I -129
73. 2Z
2.17E-05
C - 14
94. 7X
2000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
RONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
2.31E-06
I -129
71. 5Z
2.02E-06
I -139
73. 9Z
1.511-06
I -129
73 .4%
2.36E-05
C - 14
95. 11
4000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
1.62E-06
I -129
71.8Z
1.16E-06
I -129
74. IZ
7.69E-07
I -129
67. 9Z
-------
Table 6.49
CO
TIME (yr)
1.0QE401
2.00E+01
S.ODE+Oi
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.QOE+04
Dose Equivalent Rates (re»/yr) from Drinking Groundwater Contaminated by Radionuclides
Released by Borehole Drilling in BEDDED SALT
1000 Years After Repository Sealing
Drill Hit* Repository Hater
High Retardation Factors
DISTAHCE (meters)
20.00
3.69E-05
I -129
81.9Z
3.71B-05
I -129
82. OZ
3.70E-05
I -129
82.1%
1.47E-03
C - 14
97.5%
1.44E-03
C - 14
97. 5Z
1.3SE-03
C - 14
97.4%
5.81E-03
HP-23?
79.2%
4.66S-Q3
MP-237
79.01
3.31E-03
HP-237
84.71
4.59E-03
HP-237
52.51
50.00
0.0
HOME
0.0!
0,0
HONE
0.0%
2.34B-05
I -129
82. OZ
2.32E-05
I -129
82.21
2.29E-05
I -129
82.51
8.661-04
C - 14
97. SZ
7.76E-04
C - 14
97.3%
6.22E-04
C - 14
97. OS
2.28E-03
OT-237
85.81
1.68E-03
NP-237
93, n
100.00
0.0
NONE
O.OZ
0.0
NONE
o.oz
1.66E-05
I -129
81.91
1.65E-05
I -129
82. II
1.63E-05
I -129
82.42
6.26E-04
C - 14
97. 5Z
5.62E-04
G - 14
97. 4*
4.50E-04
C - 14
97.0%
2.1BE-03
MP-237
89. 2%
1.Z7E-03
NP-237
93.61
200.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
0.05
1. 17E-05
I -129
82. OZ
1.16E-05
I -129
82. 3Z
1. 111-05
I -129
83. OZ
4.16E-04
C - 14
97. 5Z
3.35E-04
C - 14
97. 2Z
1.73E-04
C - 14
95. 9%
1.35E-03
HP-237
95. 6%
500.00
0.0
NONE
O.OZ
0.0
NONE
o.oz
D.O
HONE
O.OZ
0.0
HONK
O.OX
0.0
NONE
O.OZ
7.17E-06
I -129
82. 7Z
6.75E-06
I -129
83.61
6.04B-06
I -129
84. 1Z
1.27E-04
C - 14
96. 4Z
4. 361-05
C - 14
93. 2Z
750.00
0.0
NONE
O.OZ
0,0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
MORE
O.QZ
0.0
NONE
O.OZ
5.95E-06
I -129
82.4J
5.59E-06
I -129
83.4%
5.00E-06
I -129
84. 1Z
1.16E-04
C - 14
96.81
3.93E-05
C - 14
93. 8X
1000.00
0.0
NONE
O.OZ
0.0
BORE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
5.231-06
I -129
82. OZ
4.91E-06
I -129
83.2%
4.38E-06
I -129
84. 1Z
1.13E-04
C - 14
97. 1Z
3.80E-05
C - 14
94.4%
1500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
4.12E-06
I -129
82. 8%
3.68E-06
I -129
84.02
2.73E-06
I -129
83.21
3.96E-05
C - 14
95.5Z
2000.00
0.0
NONE
O.DZ
0.0
NONE
O.OZ
0,0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
o.oz
0.0
NONE
O.OZ
3.69E-05
I -129
82.2!
3.27E-06
I -129
83. 9Z
2. 4 IE-OS
I -129
83.31
4.29E-05
C - 14
96.4%
4000.00
0.0
NONE
0.0%
0.0
N09E
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
BOHE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
2.59E-06
I -129
82. 31
l^SSE-06
I -129
84. OZ
1.20E-06
I -129
79.4%
-------
Table 6.50
CO
cn
TIHE (yr)
l.OOE+01
2.00E+01
5.00E+01
l.OOE+02
2,OOE+02
5.0QE+C2
l.OOE+03
2.00E+03
S.OOE+03
l.OOE+04
Dose Equivalent Rates
-------
CD
cn
Table 6.51
Doae Equivalent Bate* (x«o/;r) fios Drinking GrounJwater CoKtaminated by Radionuclides
Releaaed by Fault Movement
1000 Year* After Repository Sealing
Waste Directly Affected
High Retardation Factors
PISTANCE (aeters)
TIME (yr)_
l.OOE+01
2.00S+01
5.00E+01
1. OOE+Q2
2.00E+02
5.00E+02
i.OOE+03
2. 001+03
5.00E+Q3
i.QQB+04 :
20.00
1.64E-03
TC -99
94 .4%
1.74E-03
TG -99
83. SX
9.61S-03
NP-237
79.71
1.41E-Q1
NP-237
98.5%
3.28E-01
HP-237
99.31
6. 971-01
NP-237
99,.'%
1.08E+00
HP-237
99.7%
1.08E+00
HP-23?
99.5%
1,21E*00
HP-237
89 ,1Z
1.86E+00
HP-237
51. n
50.00
U69B-03
1C -99
94.5%
2.65K-03
1C -99
92,2%
1.08E-OZ
HP-237
71.1%
1.43E-01
HP-237
97.7%
3.Z9E-01
HP-237
98. 9%
6.98B-01
NP-237
99.5%
1.12E+00
HP-237
99.5%
1.71E+00
HP-237
99.6%
2.02E+00
HP-237
93,4%
2.50E+00
HP-237
64.1%
100.00
1.69S-03
TC -99
94.5%
2.65E-03
TC -99
92. 2Z
1.21E-02
HP-237
63.4%
1.44B-01
HP-237
96.81
3.30E-01
NP-237
98.5%
7.00E-01
HP-237
99,2%
1. 12E+00
HP-237
99.4Z
1.71E+00
HP-237
99. 5X
2.92E400
HP-237
95.4%
3.09E+00
HP-237
71.0%
200.00
1.69E-03
TC -99
94.5%
2.65E-03
TC -99
92.2%
1.22E-02
BP-237
62.8%
1.461-01
HP-237
95.5%
3.32E-01
NP-237
98.0%
7.02E-01
NP-237
99.0%
I.IZE+OO
HP-237
99.2%
1.71E+00
BP-237
99.4%
3.00H-00
HP-237
95.5%
3.69E+00
BP-237
75.6%
500.00
1.69E-03
TC -9»
94.5%
2.65K-03
TC -99
92.2%
1.22E-02
HP-237
62,8%
1.46S-01
HP-237
95.4%
3.35E-01
HP-237
97.1%
7.06E-01
HP-237
98.4%
1.12E+00
HP-237
98.9%
1.72E+00
HP-237
99.2%
3.00E+00
HP-237
95.4%
3.73E+00
HP-237
75. 9t
750,00
1.691-03
TC -99
94,5%
2.65E-03
TC -99
92.2%
1.22E-02
HP-237
62.81
1.46E-01
HP-237
95.4%
3.35E-01
HP-237
97. It
7.08E-01
HP-237
98.1%
1.13E+00
HP-237
93.7%
1.72E+00
HP-237
99.1%
3.00E+00
HP-237
S5.4I
3.73E+00
HP-237
75.8%
1000.00
1.69S-03
TC -99
94. 5*
2.65E-03
TC -99
92.2%
1.22E-02
HP-237
62.8%
1.46B-01
HP-237
95.4%
3.35E-01
HP-237
97.1%
7.10E-01
HP-237
97.9%
1.13S+00
MP-237
98.5%
1. 72E+00
HP-237
99.0%
3.00E+00
HP-237
95. 3X
3.73E+00
HP-237
75.8%
1500,00
1.69E-03
TC -99
94.5%
2.65E-03
TC -99
92.21
1.22E-02
HP-237
62.81
1.46E-01
HP-237
95.4%
3.35E-01
HP-237
97.1%
7. \OE-0 1
HP-;: 37
97.8%
1.13E+00
KP-237
98.3%
1.72E+00
HP-237
98.81
3.00E+DO
HP-237
95.31
3.74S+00
MP-237
75. 8Z
2000.00
1.69B-03
TC -99
94.5%
2.65E-03
TC -99
92.2%
1.22E-02
HP-237
62. 8X
1.46E-01
HP-237
95.41
3.35E-01
HP-237
97.1%
7.10E-01
NP-237
97.8%
1.131+00
HP-237
98.1%
1.72E+00
BP-237
98.7%
3.00E+00
KP-237
95.2%
3.74E+00
MP-237
75.8%
4000.00
1.69B-03
1C -99
94.5%
2.65E-03
TC -99
92.2%
1.22E-02
HP-237
62.8%
1.46E-01
HP-237
95.4%
3.35E-01
HP-E37
97.1%
7.10E-01
NP-237
97.8%
1.13E+00
HP-237
9S.OZ
1.73E+00
HP-237
98.4%
3.01E+QO
HP-237 '
95.1%
3.74E+00
HP-237
75.7%
-------
co
Table 6.52
Dose Equivalent Rate* (reo/yr) from Drinking Sroundwater Contaminated by Radiouuclides
Released by Fault Movement in GRANITE
1000 Years After Repository Sealing
Rcpooitory Water Affected
High Retardation Factors
DISTANCE (meteo)
tim (yr)
l.QOE+oi
2.QOE+01
5.00E+01
1.00E+Q2
2.00E+02
5.00E+02
l.OOE+03
2.00E+O3
5.00E+03
l.QOE+04
20.00
9.87E+00
TC -99
92. 1Z
2.38E+00
tG -99
66.4%
2.28E+02
NP-237
99.71
5.00E+02
HP-237
99.9%
4.34E+02
NP-237
99.91
4.S3E+02
NP-237
99.9%
3.87E+02
HP-237
99. 8Z
3.51E+02
HP-237
99.7%
4. 65E+02
HP-237
55,6%
8.58E+02
MI-239
31.9%
50.00
1. 061+01
TC -99
92.5%
8.26E+00
TC -99
89. a:
2.29E+02
NP-237
99.61
5.00E+02
HP-237
99. 8Z
4.35E+02
HP-237
99.8%
4.53E+02
BF-237
99. n
5.38E+02
NP-237
99.8%
6.72E+02
TO-237
99.8%
6.84E1-02
NP-237
69.8%
9.91E+02
Kf-237
29.2%
100.00
l.OGE+OL
TC -99
92. 5X
8.26E+00
TC -99
89. 8 X
2.32i+«
NP-237
98.41
5.00E+02
HP-237
99.81
4.35E+02
NP-237
99.81
4.53E+02
HP-237
99.81
5.38E+02
NP-237
99.7%
6.72E+02
HP-237
99.8%
9.79E-t02
NP-237
78,9%
I. 17E*03
HP-237
40,08
200.00
1.06E+01
TC -99
92.5Z
8.26E+00
1C -99
89.8Z
2.33E+02
BP-237
97. 8Z
5.02B+02
HP-237
99.5%
4.35E+02
MP-Z37
99.7%
4.54E+02
HP-237
99. 7Z
5.38E+02
NP-237
99. 7Z
6.73E+02
HP-237
99.7%
1.07E*03
NP-237
80.7%
1.53E*03
BP-237
54.31
500.00
1.06E+01
TC -99
92.5%
8.26E4-00
1C -99
89.8%
2,33Et02
HP-237
97. 8%
5.03E*02
HP-237
99.2S
4.37E*02
NP-237
99.2%
4.54E+02
HP-237
99.6%
5.39E+02
NP-237
99.6%
6.73E+02
HP-237
99.6%
1.07E+03
NP-237
80.6%
1.61E+03
MP-23?
56.5%
750.00
1.068+01
TC -99
92.5%
8.26E+00
TC -99
89.8%
2.33E+02
NP-237
97.81
5.03E+02
lff-237
99. 2Z
4.37E+02
NP-237
99.2%
4.55E+02
HP-237
99. 5S
5.39E+02
NP-237
99.5Z
6.74E+02
NP-237
99. 6%
1.071+03
NP-237
80.61
1.61E+03
HP-237
56.5%
1000.00
1.05E+01
TC -99
92. 5Z
8.261*00
TC -99
89.8Z
2.33E+02
HP-237
97. 8Z
5.03E+02
HP-237
99.2%
4.37E+02
NP-237
99.2%
4.55E+02
HP-237
99,4%
5.40E+02
NP-237
99.4Z
6.74E+02
BP-237
99. 5Z
1.07E+03
NP-237
80.61
1.6IE+03
HP-237
56.4%
1500.00
1.06E+01
TC -99
92.5Z
3.26E+00
TC -99
89. BZ
2.33E+02
HP-237
97. 8%
5.03E+02
HP-237
99,21
4.37E+02
NP-237
99. 2Z
4.56E+02
HP-237
99. 2Z
5.40E+02
NP-237
99.41
6.74E+02
HP-237
99.51
1.07E+03
NP-237
80.61
1.61E+03
NP-237
56.4Z
2000.00
1.06E+01
TC -99
92. 5t
8.26E+00
TC -99
89.81
2.33E+02
HP-237
97.8%
5.03E+02
HP-237
99. 2Z
4.37E+02
NP-237
99.2%
4.56E+02
HP-237
99.2%
5.41E+02
NP-237 •
99.3%
6.75E+02
HF-237
99,42
1.07E+03
NP-237
80. 5X
1.611+03
NF-237
56.4%
4000.00
1.06E+01
TC -99
92.5%
8.26E+00
TC -99
89.8%
2.33E+02
NP-237
97.8%
5.03E+02
HP-237
99. 2Z
4.37E+02
NP-237
99.2%
4.56E+02
HP-237
99.2Z
5.42E+02
NP-237
99.1%
6.76E+02
HP-237
99.2%
1.07E+03
NP-237
80.5%
1.61B+03
HP-237
56.4%
-------
In the base case, the permeability was 31.5 m/yr, which is always
higher than the permeability in this section. The high permeability
in the base case corresponds to very poor resealing of the borehole,
perhaps even to the permeability that would result from natural
plugging of an unsealed borehole with rock and dirt.
Changing the permeability of the borehole seal from the repository
to the aquifer affects only drilling releases. It affects all releases
from repository water because the permeability of the release path
affects the flow of repository water and, therefore, the rate at which
nuclides reach the groundwater. In direct hits, it affects only the
solubility-limited nuclides because the model equations for leach-
limited nuclides do not include a flow term.
6.5.1 Direct hit on waste
Table 6.53 gives the annual dose rates for a direct hit on waste.
These values can be compared with those of Table 5.7. All of the dose
rates in Table 6.53 are equal to or less than those in Table 5.7 because
the permeability is smaller in the direct hit drilling. Contaminated
areas are the same (Tables 5.11 and 6.56).
6.5.2 Granite tank
Table 6.54 gives annual dose rates for releases from the granite
tank. These annual dose rates can be compared with those of Table 5.17,
for the same base case event. For example, the maximum dose rate in
Table 6.54 is 70 rem/yr (at 10,000 years) versus 1830 rem/yr (at
1000 years) in Table 5.17. The dose rate in Table 6.54 is about a
factor of 25 less due to the lower permeability and its consequential
longer decay time.
The permeability applying to a dose at 10 meters and the 1000-year
dose time is the permeability 48 years after drilling, since borehole
permeability begins to degrade immediately after the borehole is re-
sealed, or 0.33 m/yr. The permeability for the base case is 31.5 m/yr.
The ratio of the permeabilities is 31.5/0.33 or about 95. So, the dose
188
-------
CO
ID
Table 6.53
Dose Equivalent Rate* (ren/yr) froa Drinking Groundwater Contaainated by Radionuelidea
Released by Borehole Drilling
1000 Years After Repository Sealing
Drill Hits Waste
Better-sealed Borehole
DISTANCE (aetera)
TIW (yr)
l.OCE+01
2.00B+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
20.00
1.96E-03
CS-135
58.72
1.96E-03
CS-135
58. 7Z
1.95E-03
CS-135
58.8Z
2.42E-02
SN-126
92.01
2.40E-02
SN-126
92. IZ
2.32E-02
SN-X26
92. 1Z
6.25E+02
AH-241
93. 1Z
1.51E+02
AM-241
76. 6Z
2.09E+01
AM-243
95. 5Z
7.71E+00
AM-243
99. 9Z
50.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
1.23E-03
CS-135
58.8Z
1.22E-03
CS-135
58. 9Z
1.21E-03
CS-135
59. 2Z
1.49E-02
SN-126
92.21
1.41E-02
SN-126
92. 4Z
1.26E-02
SN-126
92. 6Z
1.53E+01
AM-243
95. 5Z
5.63E+00
AM-243
99. 9Z
100.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
8.74E-04
CS-135
5B.8Z
8.67E-04
CS-135
5B.9Z
8.54E-04
CS-135
59. 2Z
1.07E-02
SN-126
92.4Z
1.02E-02
SN-126
92. 5Z
9.11E-03
SN-126
92. BZ
1.37B+01
AM-243
95.6Z
5.05E+00
AM-243
99. 9Z
200.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
6.1SE-04
CS-135
58.9Z
6.07E-04
CS-135
59. 2Z
5.81B-04
CS-135
60. 1Z
7.52E-03
SN-126
92. BZ
6.74E-03
SN-126
93. 1Z
4.86E-03
SN-126
93.61
5.74E+00
AM-243
99. 9Z
500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
3.72E-04
CS-135
60. 1Z
3.46E-04
CS-135
61.5Z
3.00E-04
CS-135
64. 2Z
3.52E-03
SN-126
94. 4Z
2.05E-03
SN-126
94. 9Z
750.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
3.08E-04
CS-135
60. 1Z
2.86E-04
CS-135
61. 5Z
2.48E-04
CS-135
64. 2Z
3.22E-03
SN-126
94. 9Z
1.88E-03
SN-126
95. 4Z
1000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
2.70E-04
CS-135
60. 1Z
2.51E-04
CS-135
61. 5Z
2.17E-04
CS-135
64. 2Z
3.12E-03
SN-126
95. 4Z
1.82E-03
SN-126
95. 8Z
1500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
2.10E-04
CS-135
61.5Z
1.82E-04
CS-135
64. 2Z
1.20E-04
CS-135
71.8Z
1.87E-03
SN-126
96. 6Z
2000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
1.86E-04
CS-135
61. 5Z
1.61E-04
CS-135
64. 2Z
1.07E-04
CS-135
71. 8Z
2.04E-03
SN-126
97. 2Z
4000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
1.25E-04
CS-135
64. 2Z
8.29E-05
CS-135
71. 8Z
4.41B-05
CS-135
81. 9Z
-------
TIKE (yr)
l.OOE+01
2.00E+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
fable S.54
Done Equivalent Rates (tcm/yr) from Drinking Groundwater Contaminated by Radionuclides
Released by Borehole Drilling in GRANITE
1000 Years After Repository Sealing
Drill Hits Repository Water
Better-sealed Borehole
DISTANCE (meters)
20.00
1.07B-04
CS-135
58.61
1. 10E-04
CS-135
58.7*
1.18E-04
CS-135
58.8%
1.36E-03
SN-126
90.31
1.73E-03
SH-126
90. 6S
2.96E-03
SH-126
91. 1Z
3.86B+01
AMh-241
93. U
4.35E+01
AM-241
76. 6%
3.88E+01
AM-243
95.5%
6.81E+01
AM-243
99. 9X
50.00
0.0
NOME
O.OZ
0.0
NONE
0.0%
7.21E-05
CS-135
58.8%
8.1 IE-OS
CS-135
58. 9%
9.99E-05
CS-135
59.2%
1.511-03
SH-126
89,2%
3.00E-03
SH-126
90, 5%
6.83E-03
SH-126
91. 5%
1,421+01
AM-243
95.51
3.42E+01
AM-243
99.81
100.00
0.0
HONE
0.0%
0.0
NONE
O.OZ
4.79E-05
CS-135
58.8*
5.42E-05
CS-135
58.9%
6.73E-05
CS-135
59.21
6.88E-04
SH-126
83.81
1.63E-03
SH-126
87.9*
4.16B-03
SN-126
90. 32
1,258+00
AM-243
98.51
1.48E+Q1
AH-243
99. 7Z
200.00
0.0
HONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
0.0%
3.40E-05
CS-135
58.9%
4.30E-05
CS-135
59.2%
7.33E-05
OS- 135
60. U
5.641-04
SH-126
76.4%
2.08E-03
SH-126
86.71
9.25E-03
SN-126
91.3%
8.37E-01
AM-243
97. OZ
500.00
0.0
NOME
O.OZ
0.0
NONE
0.0%
0.0
HONE
0.0%
0.0
NOSE
0.0%
0.0
NONE
O.OZ
3.66E-05
CS-135
60.1%
7.23S-OS
CS-135
61.5Z
1.61K-04
CS-135
64.2%
3.58E-03
SN-126
86.4Z
1.29E-02
SN-126
91.4%
750.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
0.0%
2.38E-05
CS-135
60. 1Z
5.13E-05
CS-135
61, 5Z
1.21E-04
CS-135
64. 2%
I. 648-03
SH-126
76. 5Z
8.59E-03
SN-126
89.6%
1000.00
0,0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
HONE
0.0%
0.0
NONE
O.OZ
1.57E-05
CS-135
60. OZ
3.81E-05
CS-135
61. 5Z
9.66E-05
CS-135
64. 2Z
6.03E-04
SH-126
46. 4Z
5.85E-03
SN-126
87. 1Z
1500.00
0.0
HONE
O.OZ
0,0
NONE
O.OZ
0.0
RONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
BOHE
O.OZ
2 . 15E-05
CS-135
61, 5Z
6.57E-05
CS-135
64. 2Z
2.461-04
CS-135
71. 8%
2.528-03
SN-126
76.3%
2000.00
0.0
NONE
O.OZ
0,0
NONE
O.OZ
0.0
NONE
0.0%
0.0
HONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
O.OZ
1.15E-05
CS-135
61. 5Z
4.63E-05
CS-135
64.21
1.98E-04
CS-135
71. 8Z
7.81E-04
CS-135
52. 4Z
4000,00
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
HONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
8. 688-06
CS-135
64.21
9.97E-05
CS-135
71.8*
3.04E-04
CS-135
81.9Z
-------
rate at 1000 years due to Am-241 is a factor of 95 less in this
scenario than the base ca^a -- 1830/95 = 19 rem/yr. The same iso-
topes dominate practically all the same locations on Tables 5.17 and
6.54. As the dose time increases, the value of the permeability
approaches the base case value and so the annual dose rates converge.
The area tables 5.21 and 6.56 are zero until a dose time of 1000 years.
There are no dose rates over 19.2 rem/yr for this event.
6.5.3 Brine pocket
The small size of the brine pocket and the solubility limit of the
americium produce interesting results. With a high, constant perme-
ability (base case) there is a very high flow rate and many turnovers
of the brine water per year. With this quick turnover rate which never
allows the americium to reach its solubility limit, the results are
approximately the same as those from a direct hit on two waste canisters,
However, when looking at a small, degrading permeability, the outcome
is much different. Since the flow rate is much lower, the turnover
rate is longer and the Am-241 reaches its solubility limit of 160 Ci/m
in about 50 years. As time increases, the permeability and flow
increase. The concentration remains at 160 Ci/m in the brine pocket
until decay reduces the source term to lower levels. Therefore, the
americium release rate increases with time.
At a dose time of 1000 years, when the Am-241 has traveled
20 meters, the dose rate due to the lower permeability is 3200 rem/yr,
80% from Am-241. This is about 3 times higher than the base case.
The values in the annual dose rate tables converge as the dose time
increases (Tables 5.12 and 6.55). Contaminated areas are presented on
Table 6.56, they are slightly larger than the base case (Table 5.16).
6.6 Effect of VaryingtheGroundwater Velocity
The effects of two different groundwater velocities were examined,
0.21 m/yr and 21 m/yr. These values are a factor of 10 lower and
higher, respectively, than the base case value of 2.1 m/yr. Each
191
-------
Table 6.5:.
ID
IV
TIME (yr)
t.OOE+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OQE+03
2.QOB+03
5.00E+03
I.OOE404
Dote Equivalent Rates (reo/yr) Eton Drinking Grouodwater Contaminated by Radiormclidee
Rcl«««ed by Borehole Drilling in BEDDED SALT
1000 Years After Repository Sealing
Drill Hit* Repository Water
Better-sealed Borehole
PISTANCE (aetera)
20.00
1.83E-04
OS- 135
58.61
4.71E-03
CS-135
58. It
2.89E-02
CS-135
58.8Z
1.50E-01
CS-135
S0.2X
6.37E-01
CS-135
56. 6Z
1.11E-01
CS-135
41.82
3.25E+03
AM- 241
80.5Z
6...6E+02
AM-241
76. 6Z
4.33E+Q1
AM-243
95. 5Z
1.43E-HH
AM-243
99. 9Z
50,00
0.0
HONE
0.0!
0.0
NOUS
O.OZ
9.521-03
CS-135
53.81
5.68E-02
CS-135
53.9Z
3.34B-01
CS-135
59.21
8.29E-02
CS-135
45. 7Z
2.95E-02
S8-126
84. OZ
3.58E-02
SH-126
93.01
3.611+01
AM-243
95. 6Z
1.06E+01
AH-243
99. 9X
100.00
0.0
NODE
0.0%
0.0
HONE
O.OZ
4.21B-04
C8-135
58. 8Z
1.99E-02
CS-135
58. 9Z
1.76E-01
C8-135
59.2Z
8.02E-02
OS- 135
51. OZ
1.93E-02
SM-126
82. 2Z
2.421-OZ
SH-126
92. 6Z
2.29E+02
AM-243
98.2*
9.92E+00
AM-243
99. 9Z
200.00
0.0
HONK
O.OZ
0.0
HONE
0.02
0.0
HONE
O.OZ
6.16E-04
CS-135
58. 9Z
5.51E-02
CS-135
59. 2Z
i.QlE-01
CS-135
60. IZ
1. 13E-02
SS-126
77.32
1.49E-02
SH-126
91. 4*
l.OOE-02
SK-126
93. 9Z
1. 16E402
AM-243
100.0%
500,00
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
(TONE
O.OZ
0.0
NOHK
O.OZ
0.0
HONE
O.OZ
1.70E-01
CS-135
60. IZ
2.00E-03
CS-135
61.5Z
8.56E-04
CS-135
64. 2Z
8.26E-03
SH-126
95. 2Z
3.851-03
SN-126
94. 9Z
750.00
0.0
HONS
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NOSE
O.OZ
0.0
HOHE
O.OZ
5.52E-02
CS-135
60. U
2.18S-03
CS-135
61.5Z
7.36E-04
CS-135
64. 2Z
8.12E-03
SH-126
95. 9Z
3.58E-03
SH-126
95. 5Z
1000.00
0.0
HONE
O.OZ
0.0
HOME
O.OZ
0.0
HOHE
O.OZ
0.0
HOHE
O.OZ
0.0
HOHE
O.OZ
1.82E-03
CS-135
60. IZ
5.9IE-03
CS-135
61.51
6.76E-04
CS-135
64. 2Z
4.54E-03
SH-126
93. 6Z
3.57E-03
SN-126
96. OZ
1500.00
0.0
HOHE
O.OZ
0.0
NONE
O.OZ
0.0
HOHE
O.OZ
0.0
NONE
O.OZ
0.0
HOHE
O.OZ
0.0
HOHE
O.OZ
9.45E-02
CS-135
61. 5Z
6.35E-04
CS-135
64. 2Z
2.46E-04
CS-135
71.8Z
4.27E-03
SH-126
97. 2Z
2000.00
0.0
NOHE
O.OZ
0,0
NOHK
O.OZ
0.0
HONE
O.OZ
0.0
HOHE
O.OZ
0.0
HONE
O.OZ
0.0
HONE
O.OZ
3.61E-03
CS-135
61.51
6.65E-04
CS-135
64.22
2.21E-04
CS-135
71.8Z
3.37E-03
SN-126
96.91
4000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HOHE
O.OZ
0.0
HOHE
O.OZ
0.0
HOHE
O.OZ
0.0
RONE
O.OZ
9.25E-03
CS-135
64.21
1.858-04
CS-135
71. 8Z
8.25E-05
CS-135
81.9Z
-------
Table 6.56
Area (ha*) of the Aquifer Contaminated
Above the Specified Dose Rate Levels
Following Drilling 1000 Years after Sealing
K1 = 3.15 x lO'4 (better seal)
Length of time Dose Rate Levels (rem/yr)
Event description after event (yr) 0.5 5 50 500
Direct hit on
the waste
Drill hits
granite tank
Drill hits
pocket brine
Shaft seal
release
0-500
1000
2000
5000
1 0000
0-500
1000
2000
5000
10000
0-500
1000
2000
5000
10000
0-500
1000
2000
5000
10000
0
0.33
0.30
2.09
6.08
0
0.24
0.23
0.87
1.36
0
0.36
0.32
2.44
7.34
0
0.35
0.31
2.12
6.16
0
0.27
0.23
1.18
1.28
0
0.14
0.14
0.07
0
0
0.31
0.26
1.72
4.30
0
0.29
0.25
1.23
1.65
0
0.20
0.13
0
0
0
0
0
0
0
0
0.25
0.18
0.30
0
0
0.22
0.16
0
0
0
0.06
0
0
0
0
0
0
0
0
0
0.16
0
0
0
0
0.12
0
0
0
*1 hectare (ha) = 104 square meters
193
-------
event will be examined in a separate section of this chapter. The con-
centration at a given point and time in the aquifer is inversely
proportional to v, but the nuclides will reach a given point at a
different time.
When the groundwater velocity is 21 rn/yr, nuclides with a retar-
dation factor of one or ten arrive at the 20-meter distance within ten
years after drilling. Nuclides with a retardation factor of 100, such
as the americium isotopes, travel 20 meters in 95 years, and so appear
at this distance at the 100-year dose time, rather than at the
1000-year dose time. The large annual dose rates associated with
Am-241 therefore occur earlier than they do with the base case velocity
of 2.1 m/yr. When the groundwater velocity is 0.21 m/yr, no nuclides
travel 20 meters until 95 years, so the tables show no dose rates
before this time. Am-241 does not travel 20 meters until 9500 years,
by which time it has decayed by a factor of almost two million, and so
is never an important contributor to any dose rates.
6.5-1 Release to the aquifer due to drillIng
Direct hit on waste
Tables 6.57, 5.7 and 6.58 show dose rates for a direct hit drilling
release with groundwater velocities of 21, 2.1, and 0.21 m/yr,
respectively. The maximum dose rates occur at 20 meters in all cases.
Table 6.57 shows Sn-126 dominant at 20 meters until a dose time of
100 years when the Am-241 overshadows it. The peak americiym dose rate
is 230 rem/yr in Table 6.57 compared to 580 rem/yr (93% of 625 rem/yr)
in Table 5.7 at 1000 years. Am-241 dominates until a dose time of
5000 years when Am-243 becomes the major contributor. Further down-
stream is Sn-126 slowly meandering through the porous media. The doses
at later years are lower than the base case due to diffusion.
Table 6.58 is the same event with an aquifer velocity of 0.21 m/yr.
For this scenario no nuclides reach the 20-meter distance until TOO years
after drilling. Sn-126 and Cs-135 dominate before 10,000 years,
however, the doses rates are all a fraction of a rem/yr. Higher dose
rates appear at 10,000 years, when Am-243 has traveled 20 meters.
194
-------
Am-241 is never important because of decay in the aquifer to travel
20 meters. The largest dose rate, 180 rem/yr, occurs at 20 meters and
10,000 years.
Table 6.69 shows the contaminated areas corresponding to Tables 6,57
and 6.58. When the aquifer is flowing at the high rate of 21 m/yr,
dose rate levels reach above 0.5 rem/yr at a dose time of 100 years.
Before 100 years, all areas are zero. The contaminated areas increase
markedly with time as all the nuclides spread throughout the aquifer.
The aquifer is contaminated above 0.5 rem/yr until the 10,000-year dose
time. For the slow-moving aquifer (0.21 m/yr), the entire aquifer is
below the lower dose limit of 0.5 rem/yr until the 10,000-year dose
time. The contaminated area is a factor of thirty smaller than that
associated with the fast aquifer.
Granite tank
The next two tables (6.59 and 6.60) show annual dose rates from
drilling into a granite repository when the groundwater velocities are
21 m/yr or 0.21 m/yr, respectively. The base case results were given
in Table 5.17, where the velocity was 2.1 m/yr. The highest dose rates
are from the two americium isotopes, Ara-241 gives 985£ of a 1280 rem/yr
dose rate when v = 21 m/yr, 100 years after the drilling event. After
5000 years, Am-243 gives the highest dose rate. Farther downstream the
nuclides Sn-126 and Cs-135 dominate. Table 6.60 shows that the 100-year
dose time is the first time any nuclides have traveled 20 meters in the
slow-moving aquifer.
The areas contaminated are displayed in Table 6.69. Table 6.69
shows that areas of the fast-moving aquifer become contaminated above
0.5 rem/yr 100 years after the event. This is from the Am-241 that has
traveled into the aquifer. As the dose time increases, the cumulative
areas above the given dose rate levels increase through 1000 years,
then begin to decrease at 2000 years; however, the 0.5-rem/yr level
area increases through 10,000 years. The slow-moving aquifer areas are
displayed in Table 6.69. No areas are contaminated above 0.5 rem/yr
195
-------
TIMS (yr)
l.OOE+01
2.00E+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+Q2
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
Table 6.57
Dose Equivalent Rates (rea/yr) tram Drinking Gronndwater Contaminated by Kadionuclides
Released by Borehole Drilling
1000 Years After Repository Seeling
Drill Hita Haste
High Aquifer Velocity
DISTANCE (meters)
20.00
Z.43B-03
SH-126
91.9%
2.43E-03
SN-126
9U9X
2.42E-Q3
SH-126
91.91
2.33E+nZ
AM-241
93. OX
1.99E+02
AM-241
97. 7Z
1.24E+02
AM-241
96. 5Z
5.73E+01
AM-241
93. IX
1.39E+01
AM-241
76.6%
1.92E+00
AM-243
95 .M
7.11E-01
AM-243
99 .4%
50.00
1.24E-04
CS-135
58.51
1.24E-04
CS-135
58. 5Z
1.53E-03
SH-126
91. 9Z
1.52E-03
SB- 126
92.056
1.51E-03
S8-126
92.QZ
7.95E+01
AM-241
96.51
3.6SB+01
AM-241
93. IX
8.91E+00
AM-241
76.61
1.23E+00
AM-243
95.4%
4.56E-01
AM-243
99. 5Z
100.00
8.78E-05
CS-135
58, 5Z
8.77E-05
CS-135
58.5Z
1.09B-03
SH-126
92. OZ
1.08E-03
SM-126
92. OX
1.07E-03
SH-126
92. OZ
5.76E+01
AM-241
96.5S
2.661+01
Att-241
93. 1Z
6.4SE+00
AM-241
16.61
8.93E-01
AM-243
95.4X
3.30E-01
AM-243
99. 5%
200.00
6.21E-05
CS-135
58. 5Z
6.2QI-05
CS-135
58.5Z
6.17B-05
CS-135
58.6Z
7.66E-04
SH-126
9Z.OX
7.58B-04
SH-126
92.0X
7.33E-04
SN-126
92. 1Z
1.98E+01
AM-241
93. IX
4.79B+00
AM-241
76.61
6.62E-01
AM-243
95 .4Z
2.45E-01
AM-243
99.5X
500.00
0.0
NODE
0.01
0.0
NONE
o.ot
3.918-05
CS-135
58. 6X
3.8BE-05
CS-135
58. 7X
3.B2E-05
CS-135
59.0Z
4.70E-04
SN-126
92.2Z
4.45E-04
SH-126
92. 4X
3. 991-04
SH-126
92.6%
4.83E-01
AM-243
95.4X
U78E-OI
AM-243
99.62
750.00
0.0
HONE
O.OZ
0.0
NONE
O.OX
3.20E-05
CS-135
58. 6Z
3.17E-05
CS-135
58, 7Z
3.13E-05
CS-135
59. OZ
3.88E-04
SH-126
92.3%
3.67E-04
SH-126
92. 4Z
3.29E-04
SH-126
92. 7Z
4.44E-01
AM-243
95.4Z
1.64E-01
AM-243
99. 7Z
1000.00
0.0
HONE
O.OX
0.0
HOHE
O.OZ
2.77E-05
CS-135
58.6:
2.75E-05
CS-135
58. 7Z
2.71E-05
CS-135
59. OJ
3.40E-04
SN-126
S2.4Z
3.22E-04
SH-126
92. 5Z
2.88S-04
SH-126
92. 8Z
4.33E-01
AM-243
95. 4Z
1.60E-01
AH-243
99. 7X
1500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
RONE
O.OX
2.25E-05
GS-135
58. 7Z
2.22E-05
CS-135
59.0X
2.12E-05
CS-135
59. 9Z
2.698-04
SH-126
92. 7X
2.41E-04
SH-126
92. 9Z
1.74E-04
SH-126
93. 5X
1.66E-01
AM-243
99. 8 X
2000.00
0.0
HOHE
O.OX
0.0
HONE
O.OZ
0.0
NONE
O.OZ
1.95E-05
CS-135
58. 7Z
1.93E-05
CS-135
59. OZ
1.84E-05
CS-135
59. 9%
2.3BE-04
SH-1Z6
92. BX
2.131-04
SH-126
93. OZ
1.54E-04
SH-126
93, 6X
1.B2E-01
AM-243
99.81
4000.00
0.0
HOHE
O.OX
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
1.37E-05
CS-135
59. OZ
1.31E-05
CS-135
59. 9Z
1.22E-05
CS-135
61.31
1.65E-04
SH-126
93.61
1.19E-04
SH-126
94. It
6.93E-05
SH-126
94.61
-------
fable 6.58
Tim (yr)
l.OOE+Ol
2.00E+01
5.00E+01
l.OOE+02
2.00E*02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
Equivalent Races (ren/yr) from Drinking Gronndwater Contaminated by RadionuclLdes
Released by Borehole Drilling
1000 Years After Repository Sealing
Drill Hit* Waite
Low Aquifer Velocity
DISTANCE (meters)
20.00
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NOME
O.OZ
1.95E-02
CS-135
58.71
1.93E-02
CS-135
59.0%
1.84E-02
CS-135
59.91
2.38B-01
SN-126
92.8*
2.13E-01
SN-126
93.01
1.54E-01
SN-126
93.6%
1.82E+02
Mr-243
99.81
50.00
0,0
NONE
o.oz
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
I. 18E-02
CS-135
59. 9Z
1. 10E-02
CS-135
61.31
9.51E-13
CS-135
64.01
1.11K-01
SJI-126
94. 3Z
6.49E-02
SS-126
94.8Z
100.00
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
8.56E-03
CS-135
59. 9Z
7.95E-03
CS-135
61,3%
6.89B-03
CS-135
64 .01
9.87K-02
SH-126
95 .41
5.76E-02
SN-126
95. 8Z
200.00
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OS
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
5.90E-03
CS-135
61.3%
5.11E-03
CS-135
64.02
3.38E-03
CS-135
71.6Z
6.46E-02
SH-126
97. 2Z
500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
Q.OZ
0.0
NONE
O.OZ
0.0
NONE
Q.OZ
0.0
HONE
o.oz
o.o
NONE
0.01
0.0
NONE
O.OZ
2.47E-03
CS-135
71. 6Z
1.31E-03
CS-135
81.31
750.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
2.27E-03
CS-135
71.6Z
1.21E-03
CS-135
81.5Z
1000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
2.21E-03
CS-135
71.6Z
1.18E-03
CS-135
81.51
1500.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0,0
NONE
O.OZ
0.0
RONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
1.22E-03
CS-135
81. 6Z
2000.00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.09!
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
1.34E-03
CS-135
81.61
4000,00
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0,0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NOHE
O.OZ
-------
CO
Table 6.59
'loie Equivalent EUtea (reo/yr) frois Drinking Groundwater Contaminated by [Udionuelidea
Released by Borehole Drilling in GRANITE
1000 Yeiri After Repository Sealing
Drill Hits Repository Hater
High Aquifer Velocity
DISTANCE (aeteri)
IIME (yr)
l.OOE+Ql
2.00E+01
5.00E-HH
1.00E+O2
2.00E+02
5.0QE+02
l.OOE+03
Z.OQE+03
5.00E+03
1.0UE+O4
20.00
1.33B-02
SH-126
91.81
1.35E-02
SN-126
91.81
1.41E-02
SN-126
91.92
1.28E+03
AM-241
98.0Z
1.27E+03
AM-241
97. 11
1.11E+03
AM-241
96.5*
7.42B+02
AM-241
93. IZ
2.84E+02
AM-241
76.6%
8.43E+01
AM-243
95. 52
7.05EWU
AM-243
99,9%
50.00
6.84E-04
CS-135
58.62
6.94E-04
CS-135
58.7Z
8.7*8-03
SH-126
9i. n
9.39E-03
SH-126
91. 7Z
1.06E-02
SH-126
91.81
6.19E+02
AM-241
96. 51
4,36E*02
AM-241
93. IX
1.73E+02
AM-241
76.62
5.26B+QI
AB-243
95. SZ
4.43E+01
AH-243
99,9%
100.00
4.82E-04
CS-135
58.6Z
4.89E-04
CS-135
58, 7X
5.97S-03
8H-U6
91.4Z
6.44E-03
SH-126
91.51
7.331-03
SH-126
91.6Z
3.27E+02
AM-241
96. 5Z
2.651+02
AJM-241
93.11
1. 14E+02
AM-241
76. 6%
3.63E+01
AM-243
95. 5Z
3.10E*01
AM-243
9!>,9J
200.00
3.38E-04
CS-135
58.6Z
3.43E-04
CS-135
58.7%
3.591-04
CS-135
58.81
4.26B-03
SN-126
91.0%
4.91E-03
SH-126
91.2Z
6.63B-03
SH-126
91.6Z
1.16E+02
AM-241
93.12
6.72E+01
AM-241
76.6Z
2.43E+01
AM-243
93. 5Z
2.14E+01
AM-243
99. 9%
500.00
0.0
NONE
O.OZ
0.0
HONE
O.OZ
2.22B-04
CS-135
58. 8Z
2.38E-04
CS-135
S3.9Z
2.69B-04
CS-135
59. 2Z
3.73B-03
SN-126
90.6Z
5.32E-03
SH-126
91.4Z
7.78E-03
SH-126
92. IZ
1.24E+01
AH-243
95.5Z
1.25E+01
AM-243
99. 9Z
750.00
0.0
HONE
O.OZ
0.0
NONE
O.OZ
1.78E-04
CS-135
58.8Z
1.91E-04
CS-135
S8.9Z
2.16E-04
CS-135
59. 2Z
2.70E-03
SH-126
89. 5Z
4.08E-03
SN-126
90.92
6.15E-03
SN-126
91. 8Z
7.44E+00
AM-243
96. 3Z
9.49E+00
AM-243
99.9Z
1000.00
0.0
NONE
0.02
0.0
HONE
O.OZ
1.511-04
CS-135
58.82
1.63E-04
CS-135
58.92
1.85E-04
CS-135
59. 2Z
2.02E-03
SN-126
88. OX
3.281-03
SH-126
90.3*
5.14E-03
SH-126
91.61
3.15E+00
AM-243
99. 5Z
7.48E+00
AM-243
99.82
1500.00
0.0
NOW
O.OZ
0.0
HONE
O.OZ
0.0
HONE
0.0%
1.28E-04
CS-135
58.92
1.47E-04
CS-135
59. 2Z
1.94E-04
CS-135
60. IZ
2.251-03
SH-126
83.51
3.89E-03
SH-126
91. OZ
6.78E-03
SH-126
9z. n
4.56B+00
AM-243
99. as
2000.00
0.0
HOHE
0.02
0.0
NOHS
O.OZ
0.0
HONE
O.OZ
1.07E-04
CS-135
58.92
1.23E-04
CS-135
59.22
1.65E-04
CS-135
60.12
1.52E-03
SH-126
85.52
3.09E-03
SH-126
90.22
5.72E-03
SN-126
92.51
1.75B+00
AM-243
99.52
4000.00
0.0
HOHE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NODE
O.OZ
7.39E-05
CS-135
59. 2Z
1.07E-04
CS-135
60, «
1.49E-04
CS-135
61.51
1. 18E-03
SH-126
82.42 .
3.59E-03
SH-126
91.62
5.35E-03
SH-126
93.22
-------
Table 6.60
TIME (yr)
l.OOE+01
2.QOE-MJ1
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.QOE+03
2.00S+03
5.00E+O3
l.OOE+04
Uose Equivalent Kate* (rcm/yr) frora Drinking Groundwater Contaminated by Radionuclides
Released by Borehole Drilling in GRANITE
1000 Yearn After Repository Sealing
Drill Hits Repository Hater
Low Aquifer Velocity
DISTANCE (meters)
20.00
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
mm
0.0%
1.07E-01
CS-135
58.91
1.23E-01
CS-135
59.21
1.65E-01
CS-135
60. a
1.52E+00
SN-126
85.5%
3.09E+OQ
SN-126
90.2%
5.72E+00
SN-126
92.5Z
1. 75E+03
AM-243
99.5Z
50.00
0.0
NONE
0,0%
0.0
HONE
0.0%
0.0
HOME
0.01
0.0
HOKE
0.0*
0.0
HONE
o.oz
9.18E-02
CS-135
60. IX
J..30E-01
CS-135
61.5%
1.84E-01
CS-135
64.2%
2.97E+00
SO- 126
91.0%
4.66E+00
SN-126
93. OZ
100.00
0.0
NONE
0.0%
0.0
NONE
O.OX
0.0
mm
o.oz
0.0
NOME
0.0%
0.0
NONE
O.OZ
4.84E-02
CS-135
60. 01
7;9QE-02
CS-135
51.5%
1.21E-01
CS-135
64.2%
8.99E-01
SN-126
79. 4Z
2.81E+00
SH-126
91.9%
200.00
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
0.0%
0.0
NONE
O.OZ
0,0
HONE
O.OZ
0.0
NONE
O.OZ
3.47E-02
CS-135
61. 5%
7 , 15E-02
CS-135
64. 2Z
U24B-01
CS-135
71.8%
7.59E-01
SN-126
79.31
500.00
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
o.oz
0.0
NONE
0.0%
0.0
NONE
0.01
6.34E-02
CS-135
71.3Z
9.21E-02
CS-135
81.91
750.00
0.0
NONE
0.0%
0.0
HONE
0.0%
0.0
NOME
0.0%
0.0
tfOHE
o.oz
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
0.0%
0.0
NONE
0.0%
3.82E-02
CS- 135
71.8Z
6.96E-02
CS-135
81.9%
1000.00
0.0
mm
o.oz
0.0
HONE
O.OZ
0,0
NONE
0,0%
0.0
NONE
0.0%
0.0
NONE
o.oz
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
0,0!
1.67E-02
CS-135
71.8Z
5.49E-02
CS-135
81.9%
1500.00
0.0
NONE
0,0%
0.0
worn
o.oz
0.0
NONE
O.OZ
0.0
HONK
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
DONE
0.0%
0.0
NONE
0,0%
0.0
HOME
O.OZ
3.35E-02
CS-135
81.9%
2000.00
0.0
HONE
O.OZ
0.0
NOHE
O.OZ
0.0
NONE
O.OZ
0.0
NOKE
0.0%
0.0
NOHE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
a.oz
0.0
HONE
0.0%
0.0
NONE
0,0%
1.28E-C2
CS-13S
81.91
4000.00
0.0
NOKE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
O.OZ
-------
until 1000 years, this is when Sn-126 has moved 20 meters to give dose
rates over 0.5 rem/yr. At 10,000 years the dose rates increase greatly
due to the presence of Am-243. The slower aquifer produces smaller,
but longer lasting dose rates.
Brine pocket
Table 6.61 gives the annual dose rates for the brine pocket
drilling release to the aquifer with a groundwater velocity of
21 m/yr. Sn-126 and Cs-135 dominate until about 100 years, when Am-241
first appears, giving a dose rate of 420 rem/yr. Table 5.12 gave the
base case (2,1 m/yr) results, with a maximum dose of 1150 rem/yr (93%
from Am-241). The faster flow rate causes greater diffusion and,
thereforej the peak dose rate to be lower. As Am-241 spreads and
decays in time, it falls from its peak dose rate of 420 rem/yr. By
5000 years, Am-243 has replaced Am-241 as the dominant nuclide.
Table 6.62 presents the dose rates for a slow-moving aquifer, in which
no nudities travel 20 meters until 100 years, Sn-126 and Cs-135
control all dose rates until Am-243 appears at 10,000 years,
Table 6.69 shows the contaminated areas from the event at the two
groundwater velocities. The faster flow rate produces a larger and
longer contaminated area than the base case (Table 5.16) with the
converse being true for the slower flow rate.
6.6.2 Release to the aquifer due to faulting
Direct hit on waste
Tables 6.63 and 6,64 are faulting event tables with aquifer
velocities of 21 m/yr and 0.21 m/yr, respectively. Am-241 travels the
one-meter distance which is the lower bound for integration 10 years
after the fault has opened in the fast-moving aquifer. The dose rate
builds up from 27 rem/yr at 10 years to 160 rem/yr at 200 years. As
the An-241 decays, Am-243 becomes the dominant nuclide at a dose time
of 5000 years. The slower aquifer of Table 6.64 does not become
saturated with Am-241 until 500 years after the event. Am-243
200
-------
dominates later when the Am-241 has decayed. The annual dose rates in
later years are higher than the base case since the nuclides have not
diffused as much as 1n the base case, shown in Table 5.22.
Contaminated repository water
Tables 6.65 and 6.66 show the annual dose rates from a fault line
releasing nuclides from contaminated repository water strata.
Table 6.66 has a groundwater velocity of 0.21 m/yr and a diffusion
o
constant of 1.26 m/yr . Tc-99 and Sn-126 dominate the table until
500 years. The maximum dose rate before the Am-241 has traveled
one meter (lower bound on the integral) is 40 rem/yr. Am-241 appears
at 500 years and is dominant through 2000 years. The peak dose rate in
the table, 180,000 rem/yr, occurs at 1000 years. After 5000 years,
Am-243 becomes the dominant nuclide.
Annual dose rates from the fast-moving aquifer system are dominated
by Am-241 until 5000 years. The maximum dose rate occurs at 10 years
and is a factor of two larger than in the siowing-moving aquifer
scenario. At 5000 years, Am-243 dominates as the largest contributor
but it is replaced by Pu-239 at 10,000 years.
6.6.3 Release to the aquifer due to shaft sealleakage
Tables 6.67 and 6.68 are annual dose rate tables for releases
through the shaft seals. Table 6.69 is the contaminated area table for
this scenario. The first table is for a groundwater velocity of
21 m/yr. Sr-90 dominates at less than 0.001 rem/yr up to a dose time
of 100 years. At 200 years and 20 meters, Am-241 delivers a dose rate
of about 95 rem/yr. The Am-241 continues to dominate until about
5000 years, at that point it has decayed to lower levels and the Am-243
predominates. There are no areas contaminated above 0.5 rem/yr until
100 years after the shafts are sealed. The lower flow rate case
results are in Table 6.68, the flow rate is 0.21 m/yr. The slow-moving
aquifer delays the arrival of all contaminants until the 100-year dose
time. Sr-90, Cs-1353 and Sn-126 are the important nuclides before
201
-------
Table 6.61
8
TIM Cyr)
l.OOE+01
2.00E+01
5.001401
1.DOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E*03
5.00E+03
l.UOE+04
Dose Equivalent Rates (reo/yr) from Drinking Groundwaler Contaminated by Radionuclides
Released by Borehole Drilling in BEDDED SALT
1000 Teat* After Repository Sealing
Drill Hit* Repository Water
High Aquifer Velocity
DISTANCE (cetera)
20.00
4.42E-03
SN-126
91.9%
4.453-03
SH-U6
91.92
4.44E-03
SN-126
92.01
4.27E+02
AM-241
98.02
3.64E+02
AM-241
97. »I
2.27E+02
AH-241
96.52
1.05E+02
AM-241
93.11
2.56E+01
AM-241
76.62
3.50E+00
AH-243
95.42
1.29E+00
AM-243
99.62
50.00
2.27E-04
CS-135
58.62
2.27E-04
CS-135
58.61
2.81E-Q3
SH-126
92.02
2.79E-03
SN-126
92.02
2.76E-03
SH-126
92. OZ
1.46E+02
AM-241
96. 5S
6.74E+01
AH-241
93.12
1.64E+01
Att-241
76.61
2.25B+OB
AM-243
95.4%
8.33E-01
AH-243
99.62
100.00
1.61E-04
GS-135
58. 6%
1.61E-Q4
CS-135
58.61
1.99E-03
SN-126
92.02
1.98E-03
SN-126
92.02
1.96E-03
SN-126
92.02
1.06E+02
AM-241
96.52
4.89E+01
AH-241
93. U
1.18E«-Ol
AH-241
76.62
1.63E+00
AM-243
95.52
6.01E-01
AH-243
99.72
200.00
1.131-04
CS-135
58.62
1. 14E-04
CS-135
58.62
1. 13E-04
CS-135
58.72
1.401-03
SN-126
92. OZ
1.39E-03
SH-126
92.02
1.34E-03
SN-126
92.12
3.621+01
AM-241
93.12
8.78E+00
AM-241
76.62
1.20E+00
AM-243
95.5%
4.43E-01
AM-243
99. 7Z
500.00
0.0
DONE
0.02
0.0
HONE
0.02
7.16E-05
CS-135
58.72
7.10E-05
CS-135
58.82
6.98E-05
CS-135
59.12
8.62E-Q4
SN-126
92.21
8.15E-04
SH-126
92.42
7.34E-04
SH-126
92.62
8.82E-01
AM-243
95.52
3.28E-01
AM-243
99.72
750.00
0.0
NONK
0.02
0.0
HONE
O.OZ
5.85E-05
CS-135
58.72
S.80E-05
CS-135
58.8!
5.72E-05
CS-135
59. 1Z
7.11E-04
SH-126
92.32
6.73B-04
SN-126
92.4Z
6.01E-04
SM-126
92. 62
8.10E-01
AH-243
95.52
2.98E-01
AM-243
99.82
1000.00
0.0
NONE
0.02
0.0
HONE
0.02
5.07E-05
CS-135
58.72
5.03E-05
CS-135
58.82
4.96E-05
CS-135
59.12
6.23E-04
SN-126
92.42
5.90E-04
SN-126
92.52
5.27E-04
SN-126
92.72
7.93E-01
AM-243
95.52
2.89B-01
AM-243
99.82
1500,00
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
0.02
4.12E-05
CS-135
58.82
4.06E-05
CS-135
59. U
3.8BE-Q5
CS-135
60.02
4.92B-04
SN-126
92.72
4.41E-04
SN-126
92.82
3.15E-04
SN-126
93.5Z
3.04-01
AM-243
99.8%
2000.00
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
0.02
3.58E-05
CS-135
58.82
3.52E-05
CS-135
59.12
3.37E-05
CS-135
60. OZ
4.36E-04
SH-126
92.82
3.91E-04
SH-126
93.02
2.79E-04
SU-126
93.62
3.33E-01
AM-243
99.92
4000.00
0.0
NONE
0.02
0.0
NONE
O.OZ
0.0
NONE
0.02
0.0
NONE
0.02
2. 521-05
CS-135
59. IZ
2.41E-05
OS- 135
60. OZ
2.24K-05
CS-135
61.42
3.02E-04
SN-126
93.62
2.18E-04
SN-126
94.12
1.26E-04
SN-126
94.62
-------
8
OJ
Talle 6.62
Dose Equivalent Rates (rem/yr) from Drinking Groundwater Contaminated by Radionuclides
Released by Borehole Drilling in BEDDED SALT
1000 Years After Repository Sealing
Drill Hits Repository Hater
tow Aquifer Velocity
DISTANCE (meters)
TIME (yr)
l.OOE+01
2.00E+01
5.00E+01
l.OOE+02
2.00E»02
5.00E+02
l.OOE+03
2.QOE+03
5,0QE*03
l.OOE+04
20.00
0.0
NONE
0.0%
0.0
mm
O.OJ
0.0
NOhl
O.OZ
3.58E-D2
CS-135
58. BZ
3.52B-02
GS-135
59. «
3.37B-02
CB-135
60,0%
4.36B-01
SH-126
92. SI
3.91E-Q1
SH-126
93. OZ
2.79B-01
SH-126
93.6%
3.33E*O2
AH- 2*3
99. 9Z
50.00
0.0
NONE
O.OZ
0,0
HONB
O.OZ
0.0
NONE
0.0%
0.0
NONE
0.0!
0.0
NONE
O.OJ
2. 168-02
GS-135
6(1.01
2.0JI-02
OS- 135
61.41
1.75E-02
CS-135
64,1%
2.0SE-01
SH-126
94.4X
1. WE-01
SS-126
94.9%
100.00
0.0
KONG
O.OZ
0.0
HONE
o.oz
0.0
NONE
0.0%
0.0
NONE
O.OJ
0.0
NONE
O.OZ
1.57E-02
CS-135
60. OZ
1.46E-02
CS-135
61.41
1.26E-02
GS-135
64.1%
1.81E-01
SH-126
95,4%
1.04E-01
SH-126
95.8Z
200.00
0.0
NONE
O.OZ
0.0
HOME
O.OZ
0.0
HOSE
O.OZ
0.0
NONE
Q.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
l.OSE-02
CS-135
61. 4%
9.36E-03
CS-135
64. IX
6.13E-03
CS-135
n.n
1.18E-01
SH-126
97. 2%
500.00
0.0
HOHE
O.OZ
0.0
HOW
0.0%
0.0
HONE
O.OX
0.0
NODE
0.02
0,0
NOUS
0.0%
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0,0
HONE
O.OZ
4.54E-03
CS-135
71.71
2.41B-03
CS-135
81. 7Z
750.00
0.0
HOHE
O.OZ
0.0
HOHS
O.OZ
0.0
NONE
O.GZ
0.0
NONE
O.OX
0,0
HONE
0.01
0.0
mm
O.OZ
0.0
NONE
O.OZ
0.0
NOME
O.OZ
4.17E-03
CS-135
71.7%
2.19E-03
CS-135
81.7%
1000.00
0.0
HONE
0,0%
0.0
HOHE
0.0%
0.0
NONE
O.OZ
0.0
HONE
0.0%
0.0
mm
O.OZ
0.0
HONE
O.OZ
0.0
HONE
O.OZ
0.0
HOHE
0.0%
4.05E-03
CS-13S
71.71
2.13E-03
CS-135
81.71
1500.00
0.0
HOHE
0.0%
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONB
O.OX
0.0
NONE
0.0%
0.0
HOHE
O.OZ
0.0
HOHE
O.OZ
0.0
NONE
O.OZ
O.O
NONE
0.0%
2.24E-03
OS- 135
81. 7X
2000.00
0.0
N63S
0.0%
0.0
HONE
O.OZ
0.0
NONE
0.0%
0,0
NONE
0.0%
0.0
WHS
O.OZ
0,0
NOHE
O.OZ
0.0
NONE
0.01
0.0
HOHE
O.OZ
0.0
RONS
O.OZ
2.45K-03
CS-135
Bl.7%
4000,00
0.0
NONE
0,0%
0.0
HOHE
O.OZ
0.0
NONB
O.OX
0.0
NOHB
O.OZ
0.0
NOME
0.01
0,0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HOHE
0.02
0.0
NONE
0.0%
0.9
HOKE
O.OZ
-------
Table 6.63
Dose Equivalent Rates (rea/yr) froa Drinking Groundviter Contaainsted by lUdioouclidet
Releaied by Fault Moveoent
1000 Year* After Repository Sealing
Waste Directly Affected
High Aquifer Velocity
DISTANCE (aetera)
Tim
-------
ro
o
tn
Table 6.64
Dole Equivalent R*te» (ren/yr) from Drlnkiog Grouddw«ter Contaminated by Rfldionuclides
Released by Fault Movement
1000 ¥e«ri After Repository Sealing
Haste Directly Affected
Low Aquifer Velocity
DISTANCE (metern)
TIME (yr)
l.OQE-HH
2.00E+01
5.0CE+U1
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
1.00E404
20.00
2,168-03
CS-135
53.3?
S.04E-03
CS-135
53.31
1. 19E-02
CS-135
47. 9Z
3.85E-02
SH-126
57. 2%
6.69E-02
SH-126
75.7%
6.48E+01
AM-241
96.2%
5.3ZB+02
AM-241
92.8%
2.92E+02
AM-241
75.6%
8.37E+01
AM-243
86.81
4.82E+01
AM-243
77.9%
50.00
2,168-03
CS-135
53.3*
5.04E-03
CS-135
53.3%
1.19B-02
CS-135
47. n
3.90E-02
SH-126
56.5%
7.63E-02
SN-126
66,5%
6.48E+01
AM-241
96. 2Z
5.32E+02
AM-241
92.81
2.92E+02
AM-241
75.5%
. B.38E+01
AM-243
86.7%
4.91E+01
AM-243
77.7%
100.00
2.16E-03
CS-135
53. 3%
5.041-03
CS-135
53,3%
1.19E-02
CS-135
47.9%
3.90E-02
SN-126
56,5%
7.631-02
SH-126
66.5%
6.48E+01
AM-241
96.2%
5.33E+02
AM-241
92.BS
2.92E+02
A»-241
75.5%
8.38E+01
AM-243
86.6%
4.91E+01
AM-243
77.71
200.00
2.16B-03
CS-135
53.3%
5.04E-03
CS-135
53.3%
1.19E-02
CS-135
47.9%
3.90E-02
SN-126
56.5%
7.63E-02
EH-126
66.5%
6.48E+01
AM-241
96.2%
S.33E*02
AM-241
92.8%
2.92E+02
AM-241
75.5%
8.38E+01
AM-243
86.6%
4.92E+01
&M-243
77.6%
500.00
2.16E-03
CS-135
53.3%
5.04E-03
CS-135
53.3%
1.19E-02
CS-135
47.9%
3.90E-02
SN-126
56.5%
7.63E-02
SN-126
66.5%
6.48E+01
AM-241
96.2%
5.33E+02
AM-241
92.8%
2.92E+02
AM-241 '
75.5%
8.39E+01
AM-243
86.6%
4.92E+Q1
AM-243
77.6%
750.00
2.16E-03
CS-135
53.3%
5.04B-03
CS-135
53.32
1.19E-02
CS-135
47.9%
3.90E-02
SN-126
56,5%
7.63E-02
SH-126
66.51
6.48E+01
AM-241
96.2%
5.33E+02
AM-241
92.8%
2.92E+02
AM-241
75.51
8.39E+01
AM-243
86.6%
4.92E+01
AM-243
77.6%
1000.00
2.16E-03
CS-135
53.3%
5.04E-03
CS-135
53.3%
1.19E-02
CS-135
47.9%
3.90E-01.1
SH-126
56.5%
7.63E-02
SN-126
66.5%
6.48E+01
AH-241
96.2%
5.33E+02
AM-241
92.8%
2.92E+02
AH- 241
75.5%
8.39E+01
AH-243
86.6%
4.92E+01
AM 243
77,6%
1500.00
2.16E-03
CS-135
53.3%
5.04E-03
CS-135
53.3%
1.19E-02
CS-135
47.9%
3.90E-02
SH-126
56.5%
7. 638-02
SN-126
66.5%
6.48E+01
AM-241
96,2%
5.33E+02
AM-241
92.8%
2.92S+02
AM-241
75.51
8.39E+01
AM-243
86.6%
4.92E+01
AM-243
77.6%
2000.00
2.16E-Q3
CS-135
53.3%
5.04E-03
CS-135
53.3%
1.19E-02
CS-135
47.9%
3.90E-02
SH-126
56.5%
7.63E-02
SH-126
66.5%
6.48E+01
AH-241
96.21
5.33E*02
AM-241
92.8%
2.92E+02
AM-241
75.5%
8.39E+01
AM-243
86.6%
4.92E+01
AM-243
77.6%
4000.00
2.16E-03
CS-135
53.3%
5.04E-03
CS-135
53.3%
1.19E-02
CS-135
47.9%
3.90E-02
SH-126
56. 5Z
7.63E-02
SH-126
66.5%
6.48E+01
AH-241
96.2%
5.33E+02
AM-241
92.8%
2.92E+02
AM-241
75.51
8.39E+01
AM-243
86.6%
4.92E+01
AM-243
77.6%
-------
rxs
o
Ch
Table 6.65
Dose Equivalent Rates (reu/yr) £roa Drinking Groundvater Contaminated by Hadionuclidea
Released by Fault Movement in GRANITE
1000 Yean After Repository Sealing
Repository Hater Affected
High Aquifer Velocity
DISTANCE (metera)
TIME (yr>
l.OOE+01
2.00E+01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E+03
5.00E+03
l.OOE+04
20.00
3.55E+05
AM-241
95.71
2.50B+05
AM-241
95.6X
1.64E+05
AM-241
95.41
2.78E*04
AM-241
95 .11
2.39E+04
AM-241
94.41
1.52E+04
AM-241
91.61
7,361*03
AM-241
84.2%
2.22E+03
AM-241
55.81
5.941*02
AM-243
36. 11
2.53E-MJ2
PU-239
36.71
50.00
3.55B*05
AM-241
95.71
2.SOE+OS
AM-241
95.61
1.64E+05
AM-241
95.41
1.24B+05
AM-241
95. U
9.6QB+04
AM-241
94.4Z
2.67E*04
AM-241
91.62
1.3QB+04
AM-241
84.22
3.91E+03
AH-241
55.82
1.04E+03
AM-243
36.02
4.44E+02
PU-239
36. n
100.00
3.558+05
AM-241
95. 1%
2.50E*05
AM-241
95.51
1.64E+Q5
AH-241
95.41
1.24E*05
AM-241
95. 11
9.601*04
AM-241
94. 4Z
3.99E*04
AM-241
91.6Z
l.94E*04
AM-241
84.22
5.B3E+03
AM-241
55.82
1.56E+03
AM-243
36.02
6.641*02
PU-239
36.71
200.00
3.55B+05
AM-241
95. n
2.50E*05
AM-241
95.62
1.64E+05
AM-241
95.4Z
1.24E*05
AM-241
95.11
9.60E+04
AM-241
94.42
6.47E+04
AM-241
91.6Z
2.87E+04
AM-241
84.21
8.64E*03
AM-241
55.82
2.32E*03
AM-243
36.0Z
9.84E*02
Ptl-239
36.72
500.00
3.55E+05
AM-241
95. 72
2.50E+05
AM-241
95.62
1.64E*Q5
AH-241
95.42
l.24E*05
AM-241
95. IX
9.60S+04
AM-241
94.41
6. 478+04
AM-241
91.62
3.79S+04
AM-241
S4.2Z
1.50E+04
AM-241
55.82
3.97E*03
AM-243
36.02
1.68E+03
PB-239
36.62
750.00
3.55E+05
AM-241
95.72
2.501+05
AM-241
95.62
1.64E+05
AM-241
95.42
1.248+05
AM-241
95.12
9.60E+04
AM-241
94.42
6.47E+04
AM-241
91.61
3.79E+04
AM-241
84.2Z
1.50E+04
AM-241
55. 82
5.12E+03
AM-243
36.0Z
2.17E+03
PU-239
36.72
1000.00
3.55E+05
AM-241
95.72
2.50E+05
AM-241
95. 6Z
1.64E+05
AM-241
95.42
1.24E+05
AM-241
95.12
9.60E+04
AM-241
94.42
6.47E+04
AH-241
91.62
3.79E+04
AM-241
84.22
1.50E+04
AM-241
55.82
6.20E+03
AM-243
36.02
2.64E+03
PU-239
36.72
1500.00
3.55E+05
AM-241
95.72
2.50B+05
AM-241
95.62
1.64E+05
AM-241
95.42
1.241+05
AM-241
95.12
9.601*04
AM-241
94.42
6.47E+04
AM-241
91.61
3.79S+04
AM-241
84.22
l.50E*04
AM-241
55. 82
6. 73E+03
AM-243
36.02
3.56E+03
PU-239
36. 7Z
2000.00
3.55E+05
AM-241
95.71
2.50E+05
AM-241
95. 6Z
1.64B+05
AM-241
95.42
1.24E+05
AM-241
95.12
9.60E+04
AM-241
94.42
6.47E+04
AM-241
91.62
3.791+04
AM-241
84.21
1.50B+04
AH-241
55.82
6. 73K*03
AM-243
36.01
4.56E+03
PU-239
36.72
4000.00
3.55E+05
AH-241
95.72
2.50E+05
AM-241
95.62
1.64E+05
AM-241
95.42
1.24E+OS
AM-241
95.12
9.60E+04
AM-241
94.42
6.47E+Q4
AM-241
91.62
3.79E*04
AM-241
84.22
1.50E+04
AM-241
55.82
6.73S+03
AM-243
36.0Z
4.89E+03
PU-239
36.72
-------
ro
o
•oj
Table 6.66
Dose Equivalent Rates (ren/yr) £roa Drinking Grouadvater Contaminated by Radionuclidea
Relented by Fault Movement in GRANITE
1000 Yeare After Repository Sealing
Repository Hater Affected
Low Aquifer Velocity
DISTAHCE (aetera)
TIMS (yr)
l.OOE+01
2.0QE+01
5.0QE+01
i.OOE+02
2.00E+02
5.00E+Q2
l.OOE+03
2.QOE+03
5.00E+03
l.OOE+04
20.00
5.71E+00
1C -99
52.21
1.22E+01
1C -99
52.21
2.15E+01
TC -99
48.01
4.14E+01
SB- 126
51. 61
3.42E+01
SH-126
79,5%
9.02E+04
AM-241
91.61
1.821+05
AM-241
84.2%
9.37E+04
AM-241
55.8%
3.29B+04
AM-243
36. 01
3.90B+04
P0-239
36. 81
50.00
5.71E+00
1C -99
52.2%
1.22E+01
1C -99
52.21
2.15E+01
1C -99
48. OX
4.28E+01
SB- 126
49.91
4.68B+01
SH-126
58. U
9.02E+04
AM-241
91.6%
1.82E+05
AM-241
84.21
9.37E+04
AM-241
55.81
5.29E+04
AM-243
35.91
4.32E+04
PU-239
36.8%
100.00
5.71B+00
TC -99
52.2Z
1.22E+01
1C -99
52.2%
2.15E+01
1C -99
48.0%
4.28E+01
SH-126
49.9%
4. 68E+01
SR-126
58.1%
9.02E+04
AM-241
91. 6Z
1.82E+05
AM-241
84.1%
9.37E+04
AM-241
55.8%
5.29E+04
AM-243
35. 9Z
4.32E+04
PU-239
36.8%
200.00
5.71E+00
TC -99
52.2%
1.22K+01
TC -99
52.2%
2.15E+01
TC -99
48.0%
4.28K+01
SH-126
49.9%
4.63KKU
ffl-126
58. IX
9.02E*04
AM-241
91.6%
1.82E+05
AH-241
84.1%
9.37E+04
AM-241
55.8%
5.29E+04
AM-243
35.9%
4.32E+04
PU-239
36. 8Z
500.00
5.71E+00
TC -99
52.2%
1.22E+01
TC -99
52.2%
2.15E+01
TC -99
48.0%
4.28E+01
SN-125
49.9%
4.68E+01
SH-126
58.1%
9.02E+04
AM-241
91.6%
1.82E+05
AM-241
84.1%
9.37B+04
AM-241
55.8%
5.29E+04
AM-243
35.9%
4.32E+04
PO-239
36.7%
750.00
5. 711+00
TC -99
52.2%
1.22B+01
XC -99
52.2%
2.15E+01
TC -99
48.01
4.28E+01
SH-126
49.9%
4,68E-t-01
SH-126
58.1%
9.02E+04
AM-241
91.6X
1.82E+05
AM-241
84.1%
9.371+04
AM-241
55.81
5.301+04
AM-243
35.92
4.32E+04
PU-239
36.7%
1000.00
5.71E+00
TC -99
52.2%
1.22E+01
TC -99
52.2%
2.15E+01
TC -99
48.0%
4.28B+01
SH-126
49.9%
4.68E+01
SH-126
58.1%
9.02B+04
AM-241
91.6%
1.82E+05
AM-241
84.1%
9.37E+04
AM-241
55.8%
5.30E+04
AM-243
35.9%
4.32E+04
PO-239
36.7%
1500.00
5.71E+00
TC -99
52.2%
1.22E+01
1C -99
52.21
2.15E+01
TC -99
48.0%
4.28S+01
SH-126
49.9%
4.68S+01
91-126
58. U
9.02E+04
AM-241
91.6Z
1.82E+05
AM-241
84.1%
9.37E+04
AM-241
55.8%
5.30E+04
AM-243
35.9%
4.328+04
PU-239
36. 7%
2000.00
5.711+00
TC -99
52.2%
1.22E+01
TC -99
52.21
2.15S+01
TC -99
48.0%
4.281+01
SH-126
49.9%
4.681+01
SH-126
58.1%
9.02E+04
AM-241
91.6%
1.82E+05
AM-241
84.1%
9.37E+04
AM-241
55.8%
5.30E+04
AM-243
35.9%
4.32E+04
PU-239
36.7%
4000.00
5.71E+00
TC -99
52.2%
1.22E401
1C -99
52.2%
2.15E+01
TC -99
48.0%
4.28S*01
SH-126
49.9%
4.68E+01
SH-126
58.1%
9.02E+04
AM-241
91.6%
1.82E+05
AM-241
84.1%
9.37E+04
AM-241
55.8%
5.30E+04
AM-243
35.9%
4.32E+04
PU-239
36.7%
-------
O
CO
TIME (yr)
l.OOE+Ol
2.00E*01
5.00E+01
l.OOE+02
2.00E+02
5.00E+02
l.OOE+03
2.00E*03
5.00E+03
l.OOE+04
Table 6.67
Dose Equivalent Rates (rem/yr) from Drinking Groutidwater Contaminated by Radionuclidea
Released by Shaft Seal Leakage in GRANITE
High Aquifer Velocity
DISTANCE (meters)
20.00
2.86E-05
SR -90
68. 82
8.15E-05
SR -90
60.6%
2.75E-04
SR -90
44.42
7.02E-01
AM-241
98.92
9.47E+01
AM-241
98.82
6.68E+02
AM-241
98. 32
1.14B+03
AM-241
96.52
7.48E+02
AM-241
87.02
1.74E+02
AM-243
91.42
7.Q3E+01
AM-243
99.92
50.00
1.40E-05
SR -90
69.42
4.00E-05
SR -90
68.72
1.38E-04
SR -90
53.22
3.19E-04
SH-126
55.62
9.431-04
SN-126
86.42
2.00E+02
AM-241
98.32
5.57S+02
AH-241
96.52
4.31E+02
AM-241
87.02
1.09E+02
AM-243
91.4%
4.54E+01
AM-243
99.92
100.00
5.91E-06
SR -90
69.32
2.24E-05
SS -90
68.72
7.22E-05
SR -90
65.52
1.59E-04
SH-126
40.02
5.32E-04
SH-126
83.32
1.94E+00
AM-241
98.12
2.19E+02
AM-241
96.52
2.54E-HJ2
AM-241
87.02
7.60E+01
AM-243
91.42
3.32E+01
AM-243
99.92
200.00
2.66E-07
SR -90
68.42
8.87E-06
SR -90
68.72
4.16S-05
SR -90
66.02
6.26E-05
SR -90
56.22
2.18E-04
SN-126
72.52
1.96E-03
SH-126
89.22
2.20E+00
AM-241
96.22
1.09E+02
AM-241
86.92
5.11E+01
AM-243
91.42
2.S1E+01
AM-243
99.92
500.00
0.0
HONE
0.02
0.0
NONE
0.02
1.24S-05
SR -90
66.02
2.85E-05
SR -90
57.12
3.30E-05
CS-135
40.22
6.49E-04
SN-126
80.42
3,411-03
SN-126
89.02
1.05E-02
SH-126
91.32
2.30E+01
AM-243
91.42
1. 868+01
AM-243
9S.92
750.00
0.0
HONE
0.02
0.0
NONE
0.02
3.73E-06
SR -90
66.02
1.71B-05
SR -90
57.12
2.37E-05
CS-135
40.22
2.43E-04
SN-126
59.12
2.21E-03
SH-126
86.32
7.88E-03
SH-126
90.72
8.90E+00
AM-243
95.32
1.65E+01
AM-243
99.92
1000.00
0.0
NONE
0.02
0.0
NONB
0.02
2.79E-07
SR -90
65.62
1.02E-05
SR -90
57.12
1.79E-05
CS-135
40.22
8.77E-05
CS-135
55.22
1.45E-03
SH-126
82.32
6.26E-03
SH-126
89.92
4.57E-01
AM-243
95.72
1.45E+01
AM-243
99.92
1500,00
tf.O
HONE
0.02
0.0
mm
0.02
0.0
HONE
0.02
2.88E-06
SS -90
57.12
1.08E-05
CS-135
40.12
6.16E-05
CS-135
58.62
5.52E-04
SH-126
63.42
4.19E-03
SH-126
87.92
1.31E-02
SH-126
92.72
8.39E+00
AM-243
99.92
2000.00
0.0
NONE
0.02
0.0
HONE
0.02
0.0
NONE
0.02
1.64E-07
SR -90
56.52
6.41E-06
CS-135
40.12
4.85E-05
CS-135
58.62
1.80E-04
CS-135
56.12
2.84E-03
SH-126
84.72
1.10E-02
SH-126
92.52
6.55E-01
AM-243
98.62
4000.00
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
0.02
0.0
HONE
0.02
7.76E-08
CS-135
39.32
2.17E-05
CS-135
58.62
1.01E-04
CS-135
60.12
3.18E-04
CS-135
57. OZ
6.56E-03
SH-126
91.12
6.95E-03
SH-126
94.92
-------
Table 6.68
Dose Equivalent Rstea (rem/yr) fiam Drinking Groundvater Contaminated by Radionuclides
Released by Shaft Seal Leakage in GRANITE
Lot) Aquifer Velocity
DISTANCE (meters)
rvj
o
ID
TIME (yr)
l.OOE+01
2.00E401
5.00E+01
l.OOE+02
2.00E+02
S.OOE+02
l.ODE+03
2.00E+03
5.00E+03
1.00E404
20.00
0.0
HONE
O.OX
0.0
HONE
O.OZ
0.0
NONE
O.OZ
1.64E-04
SR -90
56.51
6.41E-03
CS-135
40.12
4.85B-02
CS-135
58.6Z
1.80E-01
CS-135
56.1%
2.84E+00
SN-126
84.72
l.lOE+01
SH-126
92.52
6.35E+02
Alt-243
98.62
50.00
0.0
NONE
O.OZ
0.0
HONE
0.0%
0.0
NONE
O.OX
0.0
NONE
0.02
0.0
HONE
O.OX
1.45E-Q2
CS-135
58.62
8.25E-02
CS-135
60.12
2.50E-01
CS-135
62.92
5.11E+00
SH-126
89.92
6.50E+00
SH-126
95.0%
100.00
0.0
mm
0.0%
0.0
HONE
0.02
0.0
NONE
O.OZ
0.0
HONE
0.02
0.0
HONE
O.OZ
1.43E-04
CS-135
57.92
3.241-02
CS-135
60.02
1.47E-01
CS-135
62. 91
4.56E-01
CS-135
55. 8Z
5.05E+00
SN-126
95.32
200,00
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
ROM
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
3.27E-04
CS-135
59.7%
6.28E-02
CS-135
62.91
2.42E-01
CS-135
70. 6Z
3.92E-01
SH-126
54.6%
500.00
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.02
0.0
NONE
0.0%
1.09E-01
CS-135
70. 6Z
1.32E-01
CS-135
81.02
750.00
0.0
NONE
0.02
0.0
HONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
HONE
0.02
0.0
mn
O.OZ
0.0
NONE
0.02
0.0
NONE
O.OZ
4.40E-02
CS-135
70. 6Z
1.17E-01
CS-135
81.0Z
1000.00
0.0
HONE
O.OZ
0.0
HONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
0.02
0.0
NONE
0.02
0.0
NONE
O.OZ
0.0
HONE
O.OZ
0.0
NONE
O.OZ
E.27E-03
CS-135
70. 5%
1.03E-01
CS-135
81.0%
1500.00
0.0
NONE
0.02
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.02
0.0
NONE
O.OZ
0.0
NONE
O.OZ
5.951-02
CS-135
81.02
2000.00
0.0
HONK
0.0:1
0.0
HONB
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.0%
0.0
RONE
O.OZ
0.0
NONE
0.02
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
4.591-03
CS-135
81.02
4000.00
0.0
NONE
O.OZ
0.0
NONE
0.02
0.0
NONE
O.OZ
0.0
NONE
0.02
0.0
HONE
0.02
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
O.OZ
0.0
NONE
0.02
0.0
NONE
O.OZ
-------
Table 6.69
Area (ha*) of the Aquifer Contaminated
Above the Specified Dose Rate Levels
Following Drilling 1000 Years after Sealing
Variable aquifer velocity
Event description/
aquifer velocity
Direct hit on
waste/v = 21 m/yr
v = 0.21 m/yr
Drill hits granite
tank/v = 21 m/yr
v = 0.21 m/yr
Drill hits brine
pocket/v = 21 m/yr
Length of time
after event (yr)
0-50
100
200
500
1000
2000
5000
10000
0-5000
10000
0-50
100
200
500
1000
2000
5000
10000
0-500
1000
2000
5000
10000
0-50
100
200
500
1000
2000
5000
10000
Dose Rate Levels (rem/yr)
0.5
0
0.21
0.21
0.99
2.85
2.41
9.46
10.2
0
0.30
0
0.23
0.23
1.08
3.17
2.93
14.7
42.0
0
0.08
0.11
0.27
0.34
0
0.22
0.22
1.04
3.02
2.61
11.8
27.4
5
0
0.18
0.17
0.78
2.09
1.43
0.03
0
0
0.24
0
0.19
0.19
0.89
2.51
2.19
4.39
0.05
0
0
0
0
0.28
0
0.19
0.19
0.84
2.31
1.74
0.16
0
50
0
0.13
0.13
0.49
0.75
0
0
0
0
0.14
0
0.15
0.15
0.65
1.60
1.01
0
0
0
0
0
0
0.21
0
0.14
0.14
0.58
1.26
0.07
0
0
500
0
0.05
0.04
0
0
0
0
0
0
0
0
0.09
0.09
0.20
0.90
0
0
0
0
0
0
0
0.08
0
0.08
0.07
0.05
0
0
0
0
210
-------
v = 0.21 m/yr
Shaft seal
release/v = 21 m/yr
v =0.21 m/yr
0-5000
10000
0-50
100
200
500
1000
2000
5000
10000
0-5000
10000
0
0.32
0
0.23
0.22
1.05
3.05
2.63
11.0
23.7
0
0.31
0 0
0.25 0.17
0
0.19
0.19
0.85
2.36
1.77
0.10
0
0
0.25
0
0.15
0.14
0.60
1.34
0.86
0
0
0
0.16
0
0
0
0.08
0.08
0.08
0
0
0
0
0
0
211
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10,000 years, when Am-243 appears. The maximum dose rate is 650 rem/yr
at the 10,000-year, 2Q-r%;9ter point. No areas are contaminated until
10,000 years, and even then they are very small (Table 6.69).
6.7 Summary
Two characteristics of the repository system nave the greatest
effect on potential individual dose from high-level and transuranic
radioactive wastes after disposal in a geologic repository. These two
parameters are the solubility of radionuclides in the water in that
repository and the retardation factors for nuclides in the groundwater
(aquifer) strata. If the geochemistry is such that nuclides dissolve
in the repository water and are leach-limited rather than solubility-
limited, the isotopes of technetium, neptunium, and, especially,
Plutonium oecome available in much greater quantities. The highest
dose rates are not much affected, but the duration of contamination is
much longer because nuclides of these three elements, especially
Plutonium, persist after other nuclides, such as the americium
isotopes, have been reduced by decay.
If the nuclides are not sorbed on the rock materials of the
groundwater strata, they will move along with the groundwater
(retardation factor of one). Early doses rates will be much larger
than they would be if the nuclides were retarded and the extent of
contamination will be much greater. The highest dose rates will be
somewhat higher than they would be with retardation because more
nuclides will reach a given point together. On the other hand, if
nuclides are sorbed on groundwater strata to a greater degree than in •
the base case, they will move so slowly that a great many of them will
decay to very low levels before they have moved more than a few
meters. Doses at all points and times will be much lower than they are
in the base case and only very small portions of the groundwater will
be contaminated.
Changing the leach rate of nuclides affects the dose rates in two
ways. Early dose rates are much higher with higher leach rates, but
212
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the persistence of these doses is less because the waste in the
repository is rapidly depleted by the rapid leaching.
Changing the groundwater velocity effects the time it takes a
nuclide to reach a given point and the diffusion rates of the nuclides
in the aquifer. Larger velocities have the same effect as small
retardation factors (Note the kx/v term in all equations).
Changing the high, constant permeability to a linear, degrading
permeability generally results in smaller doses due to a lower flow
rate. The lower flow rate restricts the entry of solubility-limited
nuclides into the aquifer. In one case, the salt brine pocket, the
dose rates are higher. The tank is small and the low flow rate allows
the Am-241 to reach its solubility limit. The product of the
solubility and the flow rate is about 2.4 times that of the base case.
Changing the canister life to 1000 years causes all base case tank
releases to be zero. The direct hit cases are changed only slightly in
the leaching time a canister undergoes. A canister life of 0 years,
instant failure, causes all nuclides to begin leaching or dissolving
immediately after they are buried. The canister life has the smallest
effect of all parameters varied.
213
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REFERENCES
ADL 79 Arthur D. Little, Inc., 1979. Technical Supportof Standards
for High-level Radioactive Waste Management. Vol. A-D.,
U.S.Environmental Protection Agency (EPA 520/4-79-007),
Washington, D.C.
Ce 69 Cember, Herman, 1969. Introduction to Health Physics.
Pergamon Press, Elmsford, New York.
Du 79 Dunning, Jr., D.E., S.R. Bernard, P.J, Walsh, 6.G. Killough,
J.C. Pleasant, 1979. Estimates of Interna1 Dose Equiva1ent to
22 Target Organs for R^ionucl ides Occur ing Tn Routine
Releases from "Nuclear Fuel Cyc 1 e Fac 11111 es, Vol....II. Oak
Ridge National Laboratory (NURE6/CR-0150, Vol.2;
ORNL/NURES/TM-190/V2), Oak Ridge, Tennessee.
Ge 73 Geraghty, James J., D.W, Miller, F. Van Ber Leeden, and
F.L. Troise, 1973. Water Atlas of the United States. Water
Information Center, Inc., Port Washington, New York.
Ha 62 Harr, M.E., 1962. Groundwater and Seepage. McGraw-Hill Book
Company, New York, New York.
ICRP 59 International Commission on Radiological Protection, 1959.
ICRP Publication 2: Report of Committee II on Permissible Dose
for Internal RadiatioruPergamon Press, New York, New York.
ICRP 75 International Commission on Radiological Protection, 1975.
ICRP Publication 26: Reportof the Task Group on Reference
Man. Pergamon Press, Elmsford, New York.
Ki 76 Killough, G.G., and L.R. McKay, 1976. A Methodology for
Calculating Radiation Dojsesfrom Radioactivity Released to the
Environment^Oak Ridge NationalLaboratory (ORNL-4992), Oak
Ridge,Tennessee.
Ki 78 Killough, 6.G., D.E. Dunning, Jr., S.R. Bernard, J.C. Plesant,
1978. Estimates of Internal Dose Equivalent to 22 Target
Organs for Radionucli'des Qccuring TnRoutTne Releases from
Nuclear FueT-Cycfe Facilities, VoT. I.,Oak Ridge National
Laboratory (NUREG/0150; ORNL/NUREG/TM-190), Oak Ridge,
Tennessee.
Preceding page blank 215
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Me 78 Nelson, C.B., R. Davis, and T.W. Fowler, 1978, "A Model to
Assess Population Inhalation Exposure from A Transuranium
Element Contaminated Land Area", in Selected Topics:
Transuranium Elements in the General Environment. U.S.
Environmental Protection Agency (Technical Note ORP/CSD-78-1),
Washington, D.C.
NW 79 National Water Association, 1979. Deep Low-Yield Hells in the
United States: A Survey of Selected States. National Water
Well Association Research Facility, Worthington, Ohio.
Se 81 Serini, B.L., and Bruce Smith, 1981. Maxdose-EPA: A
Computerized Method for Estimating IndividualDoses from a
High-Level Radioactive Waste Repository. U.S. Environmental
Protection Agency(EPA/4-81-006), Washington, D.C.
SmC 82 Smith, C.B., D.J. Egan, W.A. Williams, J.M. Gruhlke, C.Y. Hung,
and B. Serini, 1982. Population Risks from Disposal of
High-Level Radioactive Haste in Geologic Repositories: Draft
Report.U.S. Environmental Protection Agency
(EPA-520/5-80-002), Washington, D.C.
SmJ 82 Smith, O.M., T.W. Fowler, and A.S. Soldin, 1980. Environmental
Pathway Models for Estimating Population Risks fromDisposal
of High-Level Radioactive Waste in Geologic Repositories:
Draft Report. U.S. Environmental Protection Agency
(EPA 520/5-80-002), Washington, D.C.
Wo 77 The World Almanac & Book of Facts 1977. Published by the
Newspaper Enterprise Association, Inc., 230 Park Avenue,
New York, New York.
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