SWRHL-92r
SUMMARY OF HYPOTHETICAL WHOLE-BODY GAMMA EXPOSURES AND
INFANT THYROID DOSES RESULTING OFF-SITE FROM PROJECT
ROVER NUCLEAR REACTOR/ENGINE TESTS AT THE
NUCLEAR ROCKET DEVELOPMENT STATION
by
R. F. Grossman
Environmental Surveillance
Southwestern Radiological Health Laboratory
U. S. Department of Health, Education
Public Health Service
Environmental Health Service
and Welfare
August 1970
This work performed under a Memorandum of
Understanding (No. SF 54 373)
for the
U. S. ATOMIC ENERGY COMMISSION
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LEGAL NOTICE
This report was prepared as an account of Government sponsored
work. Neither the United States, nor the Atomic Energy Com-
mission, nor any person acting on behalf of the Commission:
A. makes any warranty or representation, expressed or implied,
with respect to the accuracy, completeness, or usefulness of the
information contained in this report, or that the use of any inform-
ation, apparatus, method, or process disclosed in this report
may not infringe privately owned rights; or
B. assumes any liabilities with respect to the use of, or for damages
resulting from the use of any information, apparatus, method, or
proces^j disclosed in this report.
As used in the above, "person acting on behalf of the Commission"
includes any employee or contractor of the Commission, or employee
of such contractor, to the extent that such employee or contractor
of the Commission, or employee of such contractor prepares, dis-
seminates, or provides access to, any information pursuant to his
employment or contract with the Commission, or his employment with
such contractor.
001
-------
SWRHL-92r
SUMMARY OF HYPOTHETICAL WHOLE-BODY GAMMA EXPOSURES AND
INFANT THYROID DOSES RESULTING OFF-SITE FROM PROJECT
ROVER NUCLEAR REACTOR/ENGINE TESTS AT THE
NUCLEAR ROCKET DEVELOPMENT STATION
By R. F. Grossman
Environmental Surveillance
Southwestern Radiological Health Laboratory
U. S. Department of Health, Education and Welfare
Public Health Service
Environmental Health Service
Environmental Control Administration
Bureau of Radiological Health
Las Vegas, Nevada
This work performed under a Memorandum of
Understanding (No. SF-54-373)
for the
U. S. Atomic Energy Commission
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ABSTRACT
From 1959 through 1969, thirty-one nuclear reactor engine tests, conducted
at the Nuclear Rocket Development Station (NRDS) as part of Project Rover,
released airborne radioactivity which was detected in the area surrounding
the Test Range Complex (NRDS, Nevada Test Site, Tonopah Test Range, and
Nellis Air Force Range). For these tests the Southwestern Radiological
Health Laboratory (SWRHL) performed radiological monitoring and sampling.
From the radiation exposure information reported by SWRHL, whole-body gamma
exposures and infant thyroid doses were postulated for hypothetical receptors
and summarized by year and sector from NRDS. A comparison of the Radiation
Protection Standards of AEC Manual Chapter 0524 with this, summary indicated
that for each year of testing, the off-site whole-body exposures and infant
thyroid doses were below 12% and 14%, respectively, of the Radiation Pro-
tection Standards for a population sample.
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PREFACE
In accordance with Memorandum of Understanding, SF-54-373, the
Southwestern Radiological Health Laboratory (SWRHL) provides an off-site
radiological safety program for the Atomic Energy Commission in support
of nucleajp tests conducted at the Nevada Test Site (NTS) and at the
Nuclear Rocket Development Station (NRDS) which lies adjacent to NTS.
In this capacity SWRHL is responsible for the following during reactor
tests:
1. Documenting the radiological situation in off-site areas
through comprehensive environmental sampling and radiation
monitoring.
2. Assuring continuous protection of public health and safety
by determining potential and past exposures to radioactivity,
and implementing protective measures as directed by the Test
Manager, AEC.
3. Conducting a public contact and information program in the
off-site area to assure local residents that all reasonable
safeguards are being employed to protect public health and
property from radiation hazards.
4. Collecting information regarding incidents which may be
Attributed to radioactive releases to the off-site area.
Off-site .areas are considered those areas outside the boundaries of NTS, NRDS,
]i * *
the Tonop,ah Test Range, and the Nellis Air Force Range, which together are
referred f.o as the Test Range Complex.
The Southwestern Radiological Health Laboratory also represents the Bureau
of Radiological Health (BRH), Environmental Control Administration, Environ-
mental Health Services, Department of Health, Education, and Welfare, and
thereby maintains close working relationships with other components of BRH
11
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and the surrounding states. When any off-site radiological safety operation
is conducted, all appropriate parties are kept advised and all state and BRH
surveillance networks are alerted, as appropriate, to assist in documenting
levels of radioactivity.
iii
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TABLE OF CONTENTS
Page No.
Abstract i
Preface ii
List of Figures and Tables v
Introduction 1
Monitoring Methods 1
Calculations and Assumptions 3
Conclusion 5
References 13
Appendix \ £,
IV
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LIST OF FIGURES
Figure Page No.
1. Off-Site Whole-Body Gamma Exposures and Infant Thyroid 6
Doses Resulting From Project Rover Reactor/Engine Tests
From CY 1959 to 1963
2. Off-Site Whole-Body Gamma Exposures and Infant Thyroid 7
Doses Resulting From Project Rover Reactor/Engine Tests
During CY 1964
3. Off-Site Whole-Body Gamma Exposures and Infant Thyroid 8
Doses Resulting From Project Rover Reactor/Engine Tests
During CY 1965
4. Off-Site Whole-Body Gamma Exposures and Infant Thyroid 9
Doses Resulting From Project Rover Reactor/Engine Tests
During CY 1966
5. Off-Site Whole-Body Gamma Exposures and Infant Thyroid - 10
Doses Resulting From Project Rover Reactor/Engine Tests
During CY 1967
6. Off-Site Whole-Body Gamma Exposures and Infant Thyroid H
Doses Resulting From Project Rover Reactor/Engine Tests
During CY 1968
7. Off-Site Whole-Body Gamma Exposures and Infant Thyroid 12
Doses Resulting From Project Rover Reactor/Engine Tests
During CY 1969
LIST OF TABLES
Table
1. Project Rover Reactor/Engine Tests at NRDS From Which
Airborne Radioactivity Was Detected Off-Site
2. Comparison of Maximum Hypothetical Whole-Body Gamma
Exposures and Infant Thyroid Doses with Radiation
Protection Standards.
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Introduction
Thirty-one nuclear reactor/engine tests (Table 1) conducted as part of
Project Rover at the Nuclear Rocket Development Station (NRDS) between
1959 and 1969 have produced airborne radioactivity which was detected in
the areas surrounding the Test Range Complex (NRDS, Nevada Test Site,
Tonopah Test Range, and Nellis Air Force Range). The results of the radio-
logical monitoring and sampling performed by the Southwestern Radiological
Health Laboratory (SWRHL) for these tests are contained in reports for
each test series (1-18). For the purpose of comparing the radiological
effects that these tests had in off-site areas, the radiation exposure
information in these reports was summarized by year and sector from NRDS.
Monitoring Methods
When the first Kiwi reactor was tested in 1959, SWRHL operated a network
of 12 air sampling stations and a network of 28 film badge stations in the
immediate off-site area. During the reactor tests, mobile monitoring per-
sonnel (monitors) were used to supplement information from the networks.
Prior to each test, the monitors were positioned at populated locations and
on existing highways which crossed the predicted effluent trajectory to
measure radiation levels and to collect environmental samples (milk, water,
cow feed) should airborne radioactivity be released. They were equipped
with Geiger-Mueller (G-M) survey instruments, portable gamma-rate recorders
with G-M detectors and supplies for collecting environmental samples. Since
the monitors were in two-way radio contact with a control center which
followed reactor test operations and meteorological conditions, they could
be repositioned, as required.
During the following years, several changes in monitoring techniques and
expansions in SWRHL routine monitoring networks were made. Beginning in
1961, self-powered air samplers were included with the monitor's equipment,
making the air sampling coverage for tests more adaptable. In the same year,
the monitoring 'of NRDS test effluents by aircraft was begun, aiding in the
locating of effluent trajectories and in the positioning of ground monitors.
-------
Table 1. Project Rover Reactor/Engine Tests at NRDS
From Which Airborne Radioactivity Was
Detected Off-Site
Reactor/Engine
Kiwi A
Kiwi A'
Kiwi A-3
Kiwi B-1A
Kiwi B-1B
Kiwi B-4A
Kiwi B-4D
Kiwi B-4E
NRX-A2
Kiwi
NRX-A3
Phoebus 1A
NRX-A4/EST
NRX-A5
Phoebus IB
NRX-A6
Phoebus 2A
Pewee 1
XE Prime.
Experimental Plan
XVI
VII-116-B
VII-216-B
VI/A
IV
VI
IV
V
VI
IV
V
(TNT)
IV
V
VI
IV
IIB
III
IV
IVA
III
IV
III
IV
IIIA
III
IV
V
III
VC
IXA
Date
7/1/59
7/8/60
10/19/60
12/7/61
9/1/62
11/30/62
5/13/64
8/28/64
9/10/64
9/24/64
10/15/64
1/12/65
4/23/65
5/20/65
5/28/65
6/25/65
2/3/66
3/3/66
3/16/66
3/25/66
6/8/66
6/23/66
2/10/67
2/23/67
12/15/67
6/8/68
6/26/68
7/18/68
12/4/68
6/11/69
8/28/69
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In 1963, gamma-rate recorders were placed at 16 of the air sampling locations.
In 1965, Model TL-12 thermoluminescent dosimeters by Edgerton, Germeshausen
& Grier, Inc., were included in the film badge network and used off-site by
mobile monitors. However, off-site radiation exposures from reactor tests were
never detected by SWRHL with the more sensitive TLD's nor with the film badges.
The film badge and air sampling networks were expanded after the latter part
of 1961, due to the resumption of nuclear weapons testing. These off-site
networks were gradually expanded through the years so that they now include
102 off-site air sampling stations in Nevada and the Western United States,
32 gamma-rate recorders, and 9'6 fixed stations with thermoluminescent dosi-
meters. The use of film badges at the fixed dosimetry stations was terminated
in April 1970. Film badges were also assigned to a number of off-site resi-
dents beginning in 1963; the number varying from 60 to 200 with testing
activities.
Calculations and Assumptions
The modes of radiation exposure or dosage considered for the SWRHL monitoring
data were whole-body gamma exposures from cloud passage and deposition, infant
thyroid doses calculated from the hypothetical inhalation of airborne radio-
activity, and infant thyroid doses calculated from the assumed ingestion of
milk contaminated with radioiodine. Radiation exposures or doses less than
1 mR or 1 mrad, respectively, were considered to be negligible. The whole-
body exposures and infant thyroid doses are generally for a hypothetical
receptor since air samples were often taken at unpopulated locations and
infants were not present at any of the locations where air and/or milk samples
were collected.
Since film badges and TLD's,have never detected releases of airborne radio-
activity from reactor/engine tests, whole-body gamma exposures were estimated
from G-M survey instrument data. The exposure rate readings from cloud
passage and deposition were integrated from cloud arrival time to infinity
or from cloud arrival time to end of cloud passage, if no measurable deposition
occurred. No exposures were measured by film badges or TLD's for two reasons:
1) The minimum detectable exposure of the film badge and the TLD is 30 mR
and 1-5 mR, respectively; 2) film badges and/or TLD's were not always located
directly within the paths of the test effluents.
-------
The infant thyroid doses from inhalation were estimated by multiplying
the adult thyroid doses by a factor of 3. The adult thyroid doses were
determined by the product of the time-integrated concentrations of air-
borne radioiodine (pCi'sec/m ) and the following conversion factors:
mrad-m /yCi'sec
ISOTOPE
131I
132X
ESSA
0.341
0.0124
0.0922
0.0284
SWRHL
0.34
0.051
0.093
0.029
135I
The factor of 3 compensated for differences in thyroid weight and breathing
rates (m /day) between an adult and an infant (3 = [20 g/2 g][(6 m /day)/
(20 m /day)]}. The two sets of conversion factors above were used within
the referenced SWRHL reports; the first set is that used by the Air Resources
Laboratory of Environmental Science Services Administration (ESSA) (19)
in their dose predictions for each reactor/engine test, and the other set is
one derived by SWRHL (Appendix). Little difference exists between the two
132
sets of factors except for I, which contributes only a small percentage of
132
the total dose. The higher SWRHL factor is based upon the fact that Te,
132
the precursor of I, is also inhaled and contributes an increase in the
1 -JO
quantity of I which reaches the thyroid (20, 21).
The infant thyroid doses from milk ingestion were estimated from a product
of the following conversion factors and the time-integrated radioiodine con-
centrations (pCi'day/1) for those situations when milk samples were collected
at regular intervals for as long as radioactivity was detected in the milk:
ISOTOPE mrad-1/pCi'day
131I 0.019
133
I 0.0052
0.0016
When only the peak radioiodine concentrations in milk were measured, the
equivalence of 16 mrad for a 100 pCi/1 peak concentration was used (22).
-------
Once the whole-body gamma exposures and the infant thyroid doses from inhalation
and ingestion determined by the above procedures were summarized for each reactor/
engine test within a given year, the maximum exposure and dose for each test
was selected within each sector in which an exposure occurred. The maximums for
each test occurring within each year and a given sector were then summed and
entered within the appropriate sector. The blank sectors indicate that no
radioactivity was detected, or if it was detected by air samples, the potential
infant thyroid dose from inhalation was <1 mrad and no milk samples were considered
necessary. Since radiation exposures during the years 1959 through 1962 were
negligible and no reactor/engine tests released airborne radioactivity during
1963, these exposures were summarized in one illustration, Figure 1. Figures 2-7
represent the exposure and dose summaries for each calendar year 1964 through
1969.
Conclusion
Table 2 compares the Radiation Protection Standards of AEC Manual Chapter
0524 with the maximum whole-body gamma exposures and the maximum infant
thyroid doses received by hypothetical receptors during the above periods.
Table 2. Comparison of Maximum Hypothetical Whole-Body
Gamma Exposures and Infant Thyroid Doses with
Radiation Protection Standards
Radiation
Protection
Standard*
170 mrem/yr
500 mrem/yr
Maximum Whole-Body Gamma Exposure (mR)
and Infant Thyroid Doses (mrad)**
'59-'63 '64 '65 '66 '67 '68 '69
ND <1 6 20 2<1<1
< 3 24 72 36 18 13 2
Type of Exposure/Dose
Whole-body gamma exposur
Thyroid dose
*Standards are for sample of population, AEC Manual Chapter 0524.
**Units in mR and mrad are equivalent to mrem for this comparison.
For any given year the whole-body gamma exposures and infant thyroid doses were
below 12% and 14%, respectively, of the radiation protection standards for a
sample of the population.
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WINNEMUCCA
VLONE PINE
BAKERSFIELD
225° BARSTOW
ND: Not Detected
TOP NUMBER:
(PROJECT ROVER)
Hypothetical whole-body gamma exposure in mR
BOTTOM NUMBER:
Hypothetical infant thyroid dose in mrad
FIGURE 1
OFF-SITE WHOLE-BODY GAMMA EXPOSURES AND INFANT THYROID DOSES
RESULTING FROM REACTOR/ENGINE TESTS FROM CY 1959 TO 1963
-------
WINNEMUCCA
-------
WINNEMUCCA
lOOIIlES
TONOPA
NO
J \ 10\mrad
i
NO
BEATTY
LONE PJNE
BAKERSFIELD
2250 BARSTOW
ND: Not Detected
TOP NUMBER:
(PROJECT ROVER)
Hypothetical whole-body gamma exposure in mR
BOTTOM NUMBER:
Hypothetical infant thyroid dose in mrad
ESTIMATED INFANT INHALATION DOSE.
WHOLE-BODY COUNT OF SWRHL PERSONNEL INDICATED 3 mrad TO THYROID.
FIGURE 3
OFF-SITE WHOLE-BODY GAMMA EXPOSURES AND INFANT THYROID DOSES
RESULTING FROM REACTOR/ENGINE TESTS DURING CY 1965
-------
-------
WINNEMUCCA
0
<1mR
100_MIIES 3mrad
TONOPA
St. GEORGE
^•««
90°
LONE PINE
BAKERSFIELD
BARSTOW
ND: Not Detected
TOP NUMBER:
(PROJECT ROVER)
Hypothetical whole-body gamma exposure in mR
BOTTOM NUMBER:
Hypothetical infant thyroid dose in mrad
FIGURE 5
OFF-SITE WHOLE-BODY GAMMA EXPOSURES AND INFANT THYROID DOSES
RESULTING FROM REACTOR/ENGINE TESTS DURING CY 1967
10
-------
WINNEMUCCA
100_MILES
TONOPA
St. GEORGE
•^•^^
90°
LONE PINE
V)
LAS VEGAS
BAKERSFIELD
BARSTOW
ND: Not Detected
TOP NUMBER:
(PROJECT ROVER)
Hypothetical whole-body gamma exposure in mR
BOTTOM NUMBER:
Hypothetical infant thyroid dose in mrad
FIGURE 6
OFF-SITE WHOLE-BODY GAMMA EXPOSURES AND INFANT THYROID DOSES
RESULTING FROM REACTOR/ENGINE TESTS DURING CY 1968
11
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WINNEMUCCA
100J1ILES
TONOPA
St. GEORGE
LONE PINE
LAS VEGAS
BAKERSFIELD
2250 BARSTOW
ND: Not Detected
TOP NUMBER:
(PROJECT ROVER)
Hypothetical whole-body gamma exposure in mR
BOTTOM NUMBER:
Hypothetical infant thyroid dose in mrad
FIGURE 7
OFF-SITE WHOLE-BODY GAMMA EXPOSURES AND INFANT THYROID DOSES
RESULTING FROM REACTOR/ENGINE TESTS DURING CY 1969
12
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REFERENCES
Reports by Southwestern Radiological Health Laboratory, Las Vegas, Nevada
1. "Off-Site Rad-Safety, Report on Kiwi Operations," 28 July 1959.
2. "Off-Site Rad-Safety Final Report, Kiwi-A Prime and Three,ir
OTO-60-1. 1960.
3. "Kiwi B Report, United States Public Health Service Off-Site
Radiological Safety Organization." (No date given, but distributed
7 December 1961.)
4. "Off-Site Rad-Safety Final Report, Kiwi B Reactors B-1B and B-4A."
1 September 1962.
5. "Final Report of Off-Site Surveillance for the NRX-A2 Experiment."
SWRHL - 16r, 3 February 1965.
6. "Final Report of Off-Site Surveillance for the Kiwi B-4D
Experiment." SWRHL - 7r, 23 July 1964.
7. "Final Report of Off-Site Surveillance for the Kiwi B-4E Experiment."
SWRHL - 15r, 25 January 1965.
8. "Final Report of Off-Site Surveillance for the NRX-A3."
SWRHL - 18r, 8 October 1965.
9. "Final Report of Off-Site Surveillance for the Kiwi TNT Experiment."
SWRHL - 17r, 6 August 1965.
10. "Final Report of Off-Site Surveillance for the Phoebus 1A Experiment."
SWRHL - 19r, 17 January 1966.
11. "Final Report of Off-Site Surveillance for the NRX-A4/EST Test
Series." SWRHL - 30r, 19 September 1966.
12. "Final Report of Off-Site Surveillance for the NRX-A5 Test Series."
SWRHL - 32r, 15 October 1968.
13
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REFERENCES (continued)
13. "Final Report of Off-Site Surveillance for the Phoebus IB, EP-I,
EP-II, EP-III, EP-IV Reactor Test Series," SWRHL - 45r, July 1969.
14. "Preliminary Report of Off-Site Surveillance for the Phoebus IB
Test Series." 9 March 1967.
15. "Final Report of Off-Site Surveillance for NRX-A6 Test Series."
SWRHL - 78r. (To he published.)
16. "Final Report of Off-Site Surveillance for Phoebus 2A Reactor Test
Series." SWRHL - 72r. (To be published.)
17. "Final Report of Environmental Surveillance for Pewee 1, Experimental
Plans II and III, November 21 and December 4, 1968." SWRHL - 87r.
(To be published.)
18. "Final Report of Environmental Surveillance for XE Prime Reactor
Test Series." (To be published.)
Other rcferenc.cH
19. Wilson, Dean A. "An Evaluation of Radiation Prediction Models Used
by ARFRO at the NRDS." NRDS Branch, Environmental Science Services
Administration, Air Resources Field Research Office, Las Vegas,
Nevada. March 1967. p. 20.
20. "Protection of the Public in the Event of Radiation Accidents."
Proceedings of a seminar sponsored by FAO/UN, IAEA, and World
Health Organization on 18 November 1963 at Geneva, Switzerland,
1965. p. 210.
21. Le Grand, J. and Dousset, M. "Evolution DuDebit D'Equivalent DeDose
Delivree A La Glande Thyroide Apres Inhalation Instantanee De Tellure -
132 (French)." Health Physics, Vol. 12, No. 10, October 1966. p. 1407.
14
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REFERENCES (continued)
22. "Background Material for the Development of Radiation Protection
Standards." Staff Report No. 5 of the Federal Radiation Council.
Superintendent of Documents, U. S. Government Printing Office,
Washington, D. C. July 1964. pp. 14-16.
15
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APPENDIX
Calculation of Thyroid Dose
The dose rate to the thyroid may be described by the equation
dD/dt = KEA exp - (X t) where:
dD/dt = dose rate per unit time
K = dimensional constant
E = effective energy of beta and gamma radiation,
MeV per disintegration
A = concentration of radioiodine in thyroid,
yCi/g
A = effective decay constant, I/unit time
t = time after deposition in thyroid
This assumes that the radioiodine is uniformly distributed throughout the
thyroid and that the size of the thyroid is large compared to the range
of the beta particles.
The total dose is estimated by integrating the above equation from time
zero to infinity assuming D = 0 at time zero.
D = KEA / exp -(X r.t) dt
o ef f
D = <-lAeff) KEA exp -(Xgfft)
D = 0 + KEA/X ._
err
Dose from Inhalation of Radioiodines
131
The actual values for the parameters in the dose equation for I
are as follows:
= 1 rad erg 3.7xlQ4 dis 8.64x104 sec
100 erg/g X 6.24X1CP MeV x yCi'sec X day
- 51.2 rad-g-dis
MeV-yCi-d.ay
16
-------
E = 0.23 MeV (1)
A = , where:
m
X = time-integrated concentration of radioactivity,
yCi'sec/m3
/ O
B = breathing rate of standard man, 2.32 x 10 m /sec (1)
(averaged over 24 hours)
f = fraction of inhaled radioiodine reaching the
thyroid, 0.23 (1)
m = thyroid weight of standard man, 20 g
(2.32 x 10~4m3/sec)(o.23)x
20 g
1 01
Xeff = °-693/(effective half-life for I)
(°-693)/7-6
Substituting these parameters, the dose equation becomes:
= (51.2)(0.23)(2.32 x 10"4)(0.23)(7.6)x
(20)(0.693)
/ *3
D(rads) = (3.44 x 10~ rads-m )x (yCi'sec)
( yCi-sec) (m?)
or D(mrad) = (0.34 mrad'm )x (yCi'sec) rounded off to two
( yCi-sec) ( m3)
significant figures.
For the dose to a child's thyroid the above equation must be multiplied by
a factor of 3 to account for differences in thyroid weight and breathing
rates (m3/day) between an adult and a child (3 = [(20g/2g)][(6m3/day)/
(20m3/day)]}.
For other radioiodines the dose equation changes according to differences
in effective half-life and effective decay energies. The dose equations
for I and I are as follows:
17
-------
133I, D(mrad) = (0.093 mrad-m3/uCi'sec)x for E = 0.54 MeV and
A , = 0.693/0.87d
err
T
I, D(mrad) = (0.029 mrad-mJ/ijCi.sec)x for E = 0.52 MeV and
A ,, = 0.693/0.28d
err
In addition to differences in effective half-life and effective beta
132
particle energies, the dose equation for I is effected by the rapid
132
decay of I in the blood stream before it gets to the thyroid and by
132 132
the decay rate of Te, the precursor of I (2, 3). With these
132
effects incorporated, the dose equation for I becomes
-2 3
D(mrad) = (5.1 x 10 mrad'm /yCi*sec)x
132
where x is tne time-integrated concentration of Te.
Dose from Ingestion of Milk Containing Radioiodine
For ingestion, parameter A, integrated concentration of radioiodine in the
thyroid, is defined by A = CVf where,
m
C = the time-integrated concentration of radioiodine in milk,
pCi-day/1 (time-integrated concentration from time zero
to infinity assuming that the effective half-lifes of
131T 133T , 135T .... c , 01 ,
I, I, and I in milk are 5 days, 21 hours, and
6.7 hours, respectively)
V = the rate by which milk is consumed by a child one year
old or less, 1 liter/day (4)
f = fraction of ingested radioiodine reaching the thyroid,
0.3 (1)
m = thyroid weight of a child one year old or less, 2 g (4)
With the values for V, f, and m substituted,
A = (1 liter/day)(0.3) C, or
2 g
A = 0.15 liter C
dayg
18
-------
For I the dose equation D = KEA/A f becomes applicable to milk
ingestion with the above expression for A substituted.
D(mrad) = (5.12 x 10~2 mrad-g-dis)(0.23 MeV)(0.15 1)(7.6 day)C
( MeV-pCi-day) dis (dayg ) (0.693 )
or, D = (1.9 x 10~2 mrad-1) C (pCi'day)
( pCi-day) liter
For other radioiodines, the above dose equation changes according to
differences in effective half-life and effective decay energies
to become:
— 2 — 1 1 "\"\
D = (5.12 x 10 )(0.54)(0.15)(0.87) = (5.2 x 10 ) C for I and
0.693
-9 -"}
D = (5.12 x 10 Z)(0.52)(0.15)(0.28) = (1.6 x 10 J) C for
0.693
References
1. "Recommendations of the International Commission on Radiological
Protection - Report of Committee II on Permissible Dose for Internal
Radiation." ICRP-2. Pergamon Press, New York, London, Paris,
Los Angeles, 1959.
2. "Protection of the Public in the Event of Radiation Accidents."
Proceedings of a seminar sponsored by FAO/UN, IAEA, and World Health
Organization on 18 November 1963 at Geneva, Switzerland, 1965, p. 210.
3. Le Grand, J. and Dousi?et, M. "Evolution DuDebit D'Equivalent DeDose
Delivree A La Glande Thyroide Apres Inhalation Instantanee. De Tellure -
132 (French)." Health Physics, Vol. 12, No. 10, October 1966, p. 1407.
4. "Background Material for the Development of Radiation Protection
Standards." Staff Report No. 5 of the Federal Radiation Council.
Superintendent of Documents, U. S. Government Printing Office,
Washington, D. C. July 1964. pp. 14-16.
19
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DISTRIBUTION
1-15 SWRHL, Las Vegas, Nevada
16 Robert E. Miller, Manager, AEC/NVOO, Las Vegas, Nevada
17 - 18 Robert H. Thalgott, Test Manager, AEC/NVOO, Las Vegas, Nev.
19 - 20 Henry G. Vermillion, AEC/NVOO, Las Vegas, Nevada
21 - 22 D. W. Hendricks, AEC/NVOO, Las Vegas, Nevada
23 Robert R. Loux, AEC/NVOO, Las Vegas, Nevada
24 Central Mail & Records, AEC/NVOO, Las Vegas, Nevada
25 D. Hamil, Technical Library, AEC/NVOO, Las Vegas, Nevada
26 Chief, NOB/DASA, AEC/NVOO, Las Vegas, Nevada
27 P. Allen, ARL/ESSA, AEC/NVOO, Las Vegas, Nevada
28 M. Klein, SNPO, Washington, D. C.
29 R. Decker, SNPO, Washington, D. C.
30 R. Hartfield, SNPO-C, Cleveland, Ohio
31 J. P. Jewett, SNPO-N, Jackass Flats, Nevada
32 - 41 R. Nelson, SNPO-N, NRDS, Jackass Flats, Nevada
42 Wm. C. King, LRL, Mercury, Nevada
43 Roger Batzel, LRL, Livermore, California
44 J. E. Carothers, LRL, Livermore, California
45 H. T. Knight, LASL, Jackass Flats, Nevada
46 P. Gothels, LASL, Los Alamos, New Mexico
47 H. S. Jordan, LASL, Los Alamos, New Mexico
48 Charles I. Browne, LASL, Los Alamos, New Mexico
49 Wm. E. Ogle, LASL,' Los Alamos, New Mexico
50 R. E. Smith, LASL, NRDS, Jackass Flats, Nevada
51 Keith Boyer, LASL, NRDS, Jackass Flats, Nevada
52 - 54 Wm. W. Allaire, AEC/NVOO, Las Vegas, Nevada
55 G. Hoover, AEC/OCC, Mercury, Nevada
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Distribution (continued)
56 D. Gray, NRTO, NRDS, Jackass Flats, Nevada
57 J. Powell, NRTO, NRDS, Jackass Flats, Nevada
58 H. G. Simens, NRTO, Aero-jet General Corp. , Jackass Flats, Nev.
59 R. A. Smith, NRTO, NRDS, Jackass Flats, Nevada
60 G. Grandy, WANL, NRDS, Jackass Flats, Nevada
61 E. Hemmerle, WANL, Pittsburgh, Pennsylvania
62 H. Mueller, ARL/ESSA, AEC/NVOO, Las Vegas, Nevada
63 J. Doyle, EG&G, Las Vegas, Nevada
64 J. Gallimore, Pan. Am. World Airways, Jackass Flats, Nevada
65 J. Mohrbacher, Pan. Am. World Airways, Jackass Flats, Nevada
66 Martin B. Biles, DOS, USAEC, Washington, D. C.
67 R. S. Davidson, Battelle Memorial Institute, Columbus, Ohio
68 Byron Murphey, Sandia Labs. , Albuquerque, New Mexico
69 - 70 Charles L. Weaver, PHS, BRH, Rockville, Maryland
71 John C. Villforth, Director, BRH, Rockville, Maryland
72 John G. Bailey, Office of Information, BRH, Rockville, Maryland
73 Wm. Link, BRH Library, Rockville, Maryland
74 Arden E. Bicker, REECo. , Mercury, Nevada
75 Southeastern Rad. Health Lab. , Montgomery, Alabama
76 Northeastern Rad. Health Lab. , Winchester, Mass.
77 - 78 DTIE, USAEC, Oak Ridge, Tennessee
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