&EPA
>•" ""*%.
United States
Environmental Protection
Agency
Air And Radiation
(6603J)
402-R-92-005
March 1993
Computer Models Used To
Support Cleanup
Decision-Making
At Hazardous And
Radioactive Waste Sites
Recycled/Recyclable
Pnnied on paper thai contains
at laasi 50% recycled fiber
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COMPUTER MODELS USED TO SUPPORT
CLEANUP DECISION-MAKING AT
HAZARDOUS AND RADIOACTIVE WASTE SITES
March 1993
A Cooperative Effort By
Office of Radiation and Indoor Air
Office of Solid Waste and Emergency Response
U.S. Environmental Protection Agency
Washington, DC 20460
Office of Environmental Restoration
U.S. Department of Energy
Washington, DC 20585
Office of Nuclear Material Safety and Safeguards
Nuclear Regulatory Commission
Washington, DC 20555
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PREFACE
This report is the product of the Interagency Environmental
Pathway Modeling Workgroup. The Workgroup is composed of
representatives of the Environmental Protection Agency Office of
Radiation and Indoor Air and Office of Solid Waste and Emergency
Response, the Department of Energy Office of Environmental
Restoration, and the Nuclear Regulatory Commission Office of
Nuclear Material Safety and Safeguards. This report is one of
several consensus documents being developed cooperatively by the
Workgroup. These documents will help bring a uniform approach to
solving environmental modeling problems common to these three
participating agencies in their site remediation and restoration
efforts. The conclusions and recommendations contained in this
report represent a consensus among the Workgroup members.
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SURVEY QUESTIONNAIRE
The following document is the result of a mail survey using a questionnaire similar to the one presented below
Without periodic update, due to new and expanding modeling efforts, this document may soon be obsolete
Therefore, in order to keep this living document a constant source of pertinent information a is important that we
receive any additional information regarding models used in the field Please advise us of any additional models.
updated versions and/or novel applications. If you can furnish the authors with any of this information or have any
comments regarding the accuracy of the information contained herein, please lake the time to complete this survey
RADIOLOGIC AND NONRADIOLOGIC ENVIRONMENTAL TRANSFER/PATHWAY
COMPUTER MODELING ACTIVITIES
Name of Respondent: Title:
Organization:
Street
City: State: Zip Code:
Telephone (Commercial)
Site type (E.G., EPA Superfund, DOE Defense, NRC Commercial Nuclear Facilities):
Media impacted (i.e., groundwater, surface water, soils, or structures):
Name of Code (e.g., PRESTO) implemented and literature reference:
Code prepared by:
Code prepared for:
Status of modeling efforts (planned, ongoing, or completed):
in
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Radioisotopes and nonradiologic contaminants evaluated:
End-points evaluated (e.g., environmental concentration, dose commitment):
Level-of-effort expended or planned (man-months):
Have you conducted any site-specific model calibration/validation efforts: If so please briefly describe
the nature of these efforts:
Have the results of these modeling and calibration/validation efforts been published? If so where?
Other comments:
=RETURN TO=
Paul D. Moskowitz
Environmental Health Scientist
Biomedical and Environmental Assessment Group
Building 475
Brookhaven National Laboratory
Upton, New York 11973
IV
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EXECUTIVE SUMMARY
Efforts are underway to cleanup hazardous and radioactive waste sites located
throughout the U.S. To help determine cleanup priorities, computer models are being used to
characterize the source, transport, fate and effects of hazardous chemicals and radioactive
materials found at these sites. Although the U.S. Environmental Protection Agency (EPA),
the U.S. Department of Energy (DOE), and the U.S. Nuclear Regulatory Commission (NRC)
have provided preliminary guidance on the use of computer models for remediation purposes,
there is only limited directed guidance on model selection and application at radiation
contaminated sites. As a result, model selection is currently done on an ad hoc basis. This is
administratively ineffective and costly, and can result in technically inconsistent decision-
making. To identify what models are actually being used to support decision-making at
hazardous and radioactive waste sites, a project jointly funded by EPA, DOE and NRC was
initiated. The purpose of this project was to: 1) Identify models being used for hazardous and
radioactive waste site assessment purposes; and 2) describe and classify these models. This
report presents the results of this study. A mail survey was conducted to identify models in
use. The survey was sent to -550 persons engaged in the cleanup of hazardous and radioactive
waste sites; 87 individuals responded. They represented organizations including Federal
Agencies, national laboratories and contractor organizations. Although the questionnaire
received widespread distribution, we acknowledge that some important organizations (e.g.,
U.S Geological Survey) or personnel engaged in modeling at hazardous and radioactive waste
sites were not contacted. Also, because respondents were asked to participate in this effort on
a voluntary basis, it is possible that other ongoing modeling efforts were not reported. The
respondents identified 127 computer models that were being used to help support cleanup
decision-making. The identified models included: Multi-Media (41 models); Ground Water
(34 models); Air (20 models); Engineering (19 models); Surface Water (7 models),
Geochemical (5 models); and, Utilities (1 model). These models were used at EPA
(SUPERFUND), DOE (e.g., Defense, UMTRA, FUSRAP and SFMP), and NRC sites. By
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far, the largest representation was from DOE-related sites (>7S%). Many of the models in
use were developed for EPA, DOE, and NRC. However, a substantial number of models
identified (30 of the 127) were developed for other organizations. Although information was
requested about the level-of-effort spent in the modeling exercises (e.g., data assembly and
model implementation), there was little information provided by the respondents. Some
efforts in model verification, calibration and/or validation were reported for 53 of 223 model
applications. In the model applications, the overwhelming majority of the models were being
used to calculate environmental concentrations of contaminants and radiation dose
commitments. In summary, there were a few models that appeared to be used across a large
number of sites (e.g., RES RAD). In contrast, the survey results also suggested that most
cleanup efforts were using site-specific models.
VI
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CONTENTS
1. INTRODUCTION 1
2. THE SURVEY 2
3. MODEL CLASSIFICATION SCHEME 5
4. SURVEY RESULTS 7
4.1 Responses 7
4.2 Site Type 8
4.3 Sponsoring Agency 8
4.4 Media/Category 10
4.5 Level-of-Effort 10
4.6 Validation/Calibration 13
4.7 End-Points 13
4.8 Publications 13
5. DISCUSSION AND CONCLUSIONS 15
6. REFERENCES 39
APPENDIX A - BACKGROUND INFORMATION ON IDENTIFIED MODELS 59
ACKNOWLEDGMENT 103
TABLES
1. Administrative Data and Models Used 17
2. Alphabetical List of Models, Model Types and References 19
3. Model, Site Type, Contaminant, End-Point,
Effort, Validation and Publications 22
4. Model - Sponsoring Agency 27
5. Index of Existing Environmental Pathway Models 28
FIGURES
1. Mail Survey Questionnaire 3
2. Frequency of Respondent Site Type 9
3. Frequency of Models/Media Category 11
4. Frequency of Level-of-Effort 12
5. Frequency Model/End-Points 14
VII
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1. INTRODUCTION
Efforts are underway to cleanup hazardous and radioactive wastes found at
contaminated sites throughout the U.S. [e.g., U.S. Environmental Protection Agency (EPA)
Superfund Sites, U.S. Department of Energy (DOE) weapon production sites, and the Nuclear
Regulatory Commission (NRC) decommissioning sites]. The nature and extent of cleanup to
be accomplished at many of these sites will be based on initial studies [e.g., Remedial
Investigation/Feasibility Studies (RI/FS)] resulting from formally or informally negotiated
agreements between the site and the governing Agency. In these evaluations, models (e.g.,
computerized environmental pathway or engineering) are often used to characterize the source,
transport, fate and effects of hazardous chemicals and radioactive materials identified at the
sites. The models may also be used to characterize benefits of alternative remediation options.
The EPA (e.g., USEPA, 1988, 1989a, 1989b), DOE (e.g., Case et.al., 1989) and
NRC (e.g., Kozak, 1989, 1990a, 1990b) have begun preliminary efforts to .promote the
consistent use of models for site evaluation purposes at Superfund hazardous waste sites and
low-level radioactive waste repository sites, respectively. Although, the EPA, DOE and
NRC, have provided preliminary guidance on the use of computer models for remediation
purposes, there is only limited directed guidance on model selection and application at
radiation contaminated sites. As a result, model selection by site Remedial Project Managers
(RPMs), or their equivalent, is currently done on an ad hoc basis. Some of the selected
models are well known and have been subjected to wide-spread critical review. Others have
been developed for site-specific applications and have not received outside evaluation.
Consequently, Agency review of model choice and validity of the results must be done on a
site-by-site basis. This is administratively ineffective and costly, and can result in technically
inconsistent decision-making.
To assist EPA, DOE, and NRC site-level personnel (e.g., On-Scene Coordinators,
RPMs, or Site Managers) select appropriate models for RI/FS-type studies and administrators
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to review these submissions, this report: Identifies, through the use of a mail survey and a
literature review, models being used for hazardous and radioactive waste assessment purposes
at EPA Superfund, DOE, NRC and other hazardous and radioactive waste sites; and, describes
and classifies these models according to their basic characteristics.
2. THE SURVEY
A mail survey was conducted to identify radiologic and nonradiologic environmental
transfer or pathway computer models which have been used or are being used to support the
cleanup of hazardous and radioactive waste sites. The intent of the survey was to gather basic
administrative and technical information on the extent and type of modeling efforts being
conducted by EPA, DOE, and NRC at hazardous and radioactive waste sites, and to identify a
point of contact for further follow-up. The survey questionnaire is shown in Figure 1.
The survey was conducted in two phases: The first in the Spring of 1990; and, the
second in the Summer of 1991. Mailing lists were developed by compiling names and
addresses provided by EPA, DOE and NRC staff, and selecting names from various technical
reports. The lists included representatives from the three sponsoring Agencies, national
laboratories, universities and consulting engineering firms. The first questionnaire was mailed
to -350 persons; the second questionnaire was sent to an additional -200 persons.
Although the questionnaire received widespread distribution, we acknowledge that
some important organizations (e.g., U.S Geological Survey) or personnel engaged in modeling
at hazardous and radioactive waste sites were not contacted. The survey, however, attempted
to develop a "snapshot" of a dynamic, rapidly changing community of sites, models, and
responsible parties (e.g., modelers and RPMs). In this context, we believe the list of
respondents and models identified should be illustrative of those involved in the cleanup of
hazardous and radioactive waste sites.
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FIGURE 1
QUESTIONNAIRE
RADIOLOGIC AND NONRADIOLOGIC ENVIRONMENTAL TRANSFER/PATHWAY
COMPUTER MODELING ACTIVITIES AT EPA/DOE/NRC SITES
Prepared for
Office of Radiation Programs
U.S. Environmental Protection Agency
Office of Environmental Restoration and Waste Management
U. S. Department of Energy
Office of Nuclear Material Safety and Safeguards
U. S. Nuclear Regulatory Commission
Name of Respondent: Title:
Organization:
Street:
City: State: Zip Code:
Telephone (Commercial):
Site type (e.g., EPA SUPERFUND, DOE Defense. NRC Commercial Nuclear Facilities):
Media impacted (i.e., groundwater, surface water, soils, or structures):
Name of code (e.g., PRESTO) implemented:
Code prepared by:
Code prepared for:
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Status of modeling efforts (planned, ongoing, or completed):
Radioisotopes and nonradiologic contaminants evaluated:
End-points evaluated (e.g., environmental concentration, dose commitment):
Level-of-effort expended or planned (man-months):
Have you conducted any site-specific model calibration/validation efforts: If so, please briefly
describe the nature of these efforts:
Have the results of these modeling and calibration/validation efforts been published? If so,
where:
Other comments:
PLEASE RETURN COMPLETED QUESTIONNAIRE TO:
Paul D. Moskowitz
Environmental Health Scientist
Biomedical and Environmental Assessment Group
Brookhaven National Laboratory
Upton. New York 11973
(516 282-2017) (FTS 666-2017)
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3. MODEL CLASSIFICATION SCHEME
While the survey was being conducted, we concluded early-on that a classification
scheme would be needed to organize the discussions on modeling capabilities due to their wide
range of focus. One way to classify models is according to their major purpose (e.g.,
environmental transport, accidents etc.). Another common way to classify models is by the
environmental media they simulate (e.g., air, soil, surface water or ground water). Models
could also be broken down into those groups which simulate only the physical transport of a
contaminant through air, soil or water; and those which follow the contaminant through the
food chain to man, producing estimates of dose or risk. A classification scheme based on a
combination of these categories is used here.
The major categories used in this report are:
1. Multi-Media;
2. Air;
3. Surface Water;
4. Ground Water;
5. Aqueous Geochemistry;
6. Engineering/Performance/Accident;
7. Radiation Dose;
8. Utilities (Model Support Software).
The first four classes of models are concerned with the transport and fate of hazardous
and radioactive materials in the environment. In the first class, Multi-Media models, some
attempt is made to integrate several possible media (e.g., air, ground water, food chain, soil,
etc.) into one simulation. Subclasses within the first group include Hazard Ranking,
Radioactive Fate and Transport, General Purpose and Food Chain. Hazard Ranking models
rank waste sites based on the risks they may present to the public; the numbers produced by
these models are used relative to each other, and are not used to estimate risk at individual
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facilities. In contrast, Radioactive Materials Fate and Transport, and General Purpose models
provide an estimate of the environmental transport, exposure and risk presented by releases of
radioactive materials or other types of pollutants, respectively.
Transport models predict the physical movement of contaminants through one media
(e.g., air, surface water and ground water). Air models sometimes include consideration of
other pathways (e.g., soil deposition and agricultural uptake). Similarly, many ground and
surface water models evaluate unsaturated-zone transport of contaminants. This report,
however, groups models as air, surface or ground water on the basis of their primary focus,
rather than their potential applications or ancillary use. If the transport models predict
contaminant transfer among the different media, they have been placed in the Multi-Media
class.
The other four classes of models are used for more-specific purposes. Aqueous
Geochemical and Hydrogeochemical models attempt to establish the relative abundance or
concentration of various contaminant species. Geochemical models are often used to predict
whether a given dissolved pollutant will be precipitated during transport in surface or ground
water; or conversely, whether a solid pollutant might be dissolved under certain aqueous
conditions.
The group of models classified as Engineering/Performance/Accident models evaluate
safety and the potential for contaminant transport based on an analysis of human-engineered
structures. Engineering models calculate volumes, slopes or stresses of engineered or natural
structures. Accident models estimate the transport and ultimate effects of radionuclides
released during an accident in a nuclear reactor or waste storage sites. Performance models
assess the capability of engineered structures designed to isolate waste from the environment;
models designed to assess the risk associated with releases from landfills and other engineered
facilities; and models used to estimate the levels of contaminants that can remain after cleanup
based on environmental transport and risk information.
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Radiation dose models determine the amount of shielding needed in a radiation area, or
calculate radiation dose from radioactive substances transported through the environment as
established by the use of other transport models. The last category, Utilities, includes software
which supports or enhances the use of the aforementioned classes of models.
4. SURVEY RESULTS
4.1 Responses
A total of 87 individuals responded; 61 in Phase 1, and 28 in Phase 2 (two individuals
responded to both surveys). The persons and organizations responding to the survey are listed
in Table 2, along with the models identified by each respondent. Model application responses
were received from individuals, both modelers and division heads supervising- a group of
modelers, representing 38 different companies, facilities or Federal Agency Offices. In total,
these respondents identified 127 different models. In later sections to this chapter further
information on the models, the media impacted, etc., is presented.
Some of the organizations responding to the survey are DOE National Laboratories
with strong research and development programs; and, a few of the models identified were
developed by the respondents and applied at other sites. To the extent possible, these
development responses are not included in the analysis of the survey responses. The
information provided on model development, however, has been used in preparing Appendix
A which gives a brief description of each of the models identified in the survey, including the
sponsoring agency, a description of the model, and relevant references. These survey results
can provide useful information for expanding and updating the knowledge-base on models
being applied in the remediation of radiation contaminated sites.
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Data from the survey allows for an analysis of both the type and numbers of unique
models identified, as well as the number of model applications falling into a given category.
Some models are used at many sites, particularly in the DOE community. In contrast, the
survey also suggests that most sites were using models which were not reported in use
elsewhere. Table 3 alphabetically lists the reported models. This Table also presents primary
literature references for most of the models and gives a quick indicator of the model type
(e.g., air and ground water). Finally, the Table indicates whether the model can be used for
radioactive substances and whether it is a detailed or screening-level model. Codes used for
the purpose of modeling non-radioactive substances were included in this table because such
models are often used for radioactive materials with very long half-lives (e.g., K-40) relative
to their transit time.
Table 4 lists the site type at which each model was applied (see section 4.2) as well as
which contaminants were being modeled at the site, the end-points of the modeling effort (see
section 4.7), and the amount of time needed to complete this effort (see section 4.5). Finally,
the Table shows whether the model has been calibrated/validated at the site and whether these
results have been published (see sections 4.6 and 4.8, respectively).
4.2 Site Type
In Figure 2 the types of sites (e.g., DOE Defense, EPA Superfund) under investigation
are summarized. By far the largest representation is from DOE-related sites. These account
for more than 75 % of the reported site-types.
4.3 Sponsoring Agency
As Table 5 indicates, many of the models identified were developed by or for EPA
(e.g., AIRDOS, RISC, PRESTO, RADRISK), DOE (e.g., BIOTRAN, MEPAS, RESRAD,
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Frequency of Respondent Site Type
DOE DEFENSE
EPA/SUPERFUND
O
C
jo
m
to
DOE UMTRA
NRC
DOE/NATL LAB
DOE/SFMP DOE/FUSRAP
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RSAC) or the NRC (e.g., MACCS, RAECOM, UDAD). A few of the models were
developed for use at a specific site by the individual organizations. Note that the number of
models sponsored by groups other than the three sponsoring Agencies is substantial (30 of
127). The "Other" group includes private corporations, universities, the U.S. Geological
Survey, U.S. Department of Agriculture, Canadian government agencies, State agencies, and
non-profit groups. It is evident that independent model development and support is vigorous.
4.4 Media/Category
There are two important ways to look at the data further; by model, or by application.
The models identified in the survey responses were categorized into the groupings discussed in
Section 3. Figure 3 shows the distribution of the unique models identified among these
categories. The Multi-Media category is the largest class where 41 models were reported.
This was closely followed by the Ground Water transport category where 34 different models
were identified. There were 20 reported Air models and seven reported Surface Water
models. Engineering models which include Performance Assessment, Accident and Radiation
Dose models were the next largest category with 19 models identified. Five Geochemical
models and one Utility model were also reported.
4.5 Level-of-Effort
The level-of-effort required for the completion of a modeling task appears to be project
specific, as opposed to model specific. The data obtained from both surveys show a wide-
range of man-months needed to complete a project. However, most respondents failed to
answer this question. Figure 4 presents these data in groups of man-months needed to
complete each reported modeling effort.
10
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Frequency of Moa Js/Media Category
Engineering
Geochemical
Ground Water
Multi-Media
Utilities
Surface Water
* Including Performance, Accident & Rad. Dose Models
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Frequency of Level of Effort
LJJ
Q
O
O
cc
LJJ
CO
120
100
80
O
d
PQ
m
unknown
0.5-6 6.5-12 12.5-24 24-36
TIME IN MAN MONTHS
36+
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4.6 Validation/Calibration
Site-specific model validation/calibration efforts were conducted for 56 model
applications. No validation/calibration studies were reported for the remaining 167
applications. This survey does not, however, describe how, or what level-of-effort was spent
on validation/calibration. Further inquiry is needed here to determine which models have been
validated/calibrated, and what was actually done.
4.7 End-Points
Figure 5 depicts the frequency of end-points being evaluated by the reported models.
The overwhelming majority of models are being used for the more general purpose of finding
environmental concentrations of contaminants and radiation dose commitment. Several more
task specific models are also reported with less frequency.
4.8 Publications
Results of the reported modeling and validation/calibration efforts of 56 applications
were published in various journals and papers. For 167 of the model applications there were
either no publications or no response to the survey question regarding publication.
13
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Frequency of Models/End Points
Env. Cone.
Dose Commit.
Other
Other includes: Water Levels, Flow Rates, Riprap Sizing,
Radon Emanation, etc., (see Table 4).
Q
Flow Rate
Risk Assess.
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5. DISCUSSION AND CONCLUSIONS
In any voluntary survey it is essential to question the representativeness of the results.
In this context, the results of the two surveys reported here can be compared with each other
and with previously published technical literature.
In comparing the data collected within the two surveys reported here, one of the most
striking aspects of the results is the small overlap between the two. As Table 6 indicates only
17 models (13% of the total) were reported in both surveys. While this may suggest that each
of the surveys sampled distinctly different populations, there is one very important reason that
this might not be true. That is, we had originally hypothesized that because no formal
guidance for model use exists, models would be chosen on an ad hoc, site-by-site basis. This
hypothesis appears to be correct. Approximately 60% of the identified models in both surveys
were used at only one site. This could also imply that there may be a substantial amount of
model redundancy, especially in the application of General Purpose or Multi-Media models.
Based on published literature which includes surveys (e.g., Mangold and Tsang, 1991),
review articles (e.g., Case, 1989) and technical literature on model development and
application oriented studies, we know that many other models exist other than the models
identified in this survey. In Table 6, we list and categorize many of these "unidentified"
models. Whether these models are actually being used to support cleanup decisions remains
unanswered. We speculate that these models were not identified because of the dynamic
nature of the modeling community in which models and model applications are constantly
being upgraded and changed. An index of known environmental pathway models,
extrapolated from all referenced literature and revues, and the agency which sponsored their
development is also presented in Table 6. Models reported in the current survey represent
approximately 25% of the known models used in environmental pathway analysis. One
important example of an "unidentified" model is FEMWATER/FEMWASTE. No users of the
15
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model were identified in the survey, yet the use of FEMWATER/FEMWASTE has been
reported in the literature (Sullivan and Suen, 1989).
In conclusion, it is clear that a unified approach to model selection is needed.
Ultimately, this will reduce administrative cost, while improving the technical quality of the
decision-making process. Proactive guidance from the sponsoring Agencies for model
selection is preferable to retroactive correction and improvement, through modification, of an
inappropriately applied model.
16
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TABLE 1 - Admnlitratlve Data and Modab Used
Count Name
Organ liallon
Street AdoVmi
Clt>
State Zip
Telephone Models U«ed
1
3
2
4
I
t
7
8
9
10
11
12
13
14
19
16
17
18
19
20
21
22
23
24
25
26
27
28
29
30
31
32
33
34
35
38
37
38
39
40
41
42
43
44
David Abbol
Peter F Andenon
Richard W Arnteth
Burton R Baldwin
MireelP Bercernon
BC Blaytock
Willing C Bo-den
L.SCahn
DanialG Carbgno
DcnimJ Can-
Young- Soo Chang
David A Charlion
Charles L Cbeever
Chriinne Daily
Christine Daily
Jerry D Davis
Jerry D Davu
TR Decker
Nicolella DiFortc
? C Doctor
Jamei G Droppo Jr
LuaA Dtrbam
RoyEckart
Kenneth J Eger
Mac Ennu
David E Fans
Michael J Payer
Alan Fcllman
Joe Frailer
GaryGaillol
Bruce Gallaher
David Galleios
Richard O Gilbert
GKTKIO N Gnunnoli
Tim Geerms
Mart Hansen
John Hate low
Marvin W Henderson
Marvin W Henderson
Marvin W Henderson
Marvin W Henderson
Job Hlavacck
F.O Hoffman
J D Hooter
Chens Yens Huns
Victor J Janosik
dark Kaulsky
Mark E Kaye
iliabeth Keicher
EGAGMoundAppledTceh
Geo1>sni. Inc
Sccnce Applications Inte
ECAC Idaho
Pacific Northwest Lab
Oak Ridse National Lab
Bechtcl National. Inc
UNCGeotech
EG&G/mound applied Techno
Feed Materials Prod Or
Arsonne National Lab
CHEM- NUCLEAR ENV.Svcs
Argonne National Lab
US NRC
U.S NRC
Weslinshouse Hanfcrd Co
Wcslinshouse Hanfcrd Co
U S NRC Rll
Office of the Regional Ad
Pacific Northwest Ub
Pacific Northwest Lab
Argonne National Lab
Feed Materials Prod Or
EBASCO Envronnenul
Los Alamos National Lab
Feed Mater la Is Prod Co-
Pacific Northwest Lab
Rad Branch. U5EPA Reg 2
EGAG Idaho Inc
IT Corp
Los Alamos Nail Lab
SNLOrg64l6
Pacific Northwest Lab
USNRC
Jacobs Engineer ins Group
USEPA
Savannah River Laboratory
M K- Ferguson Company
MK— Ferguson Company
M K- Ferguson Company
M K- Ferguson Company
M K- Ferguson Company
Oak Ridge National Lab
Weitinithouse Hanfcrd Co
USEPA. Office Rad Pros
EPA
UNCGeotech
Bechtcl National. Inc
EPAR*
P O Boi 3000
46050 Manckm Plaza
Ml Laboratory Rd
P O Boi 1«2S
PO Boi 999. MS K6-77
P.O Boi 2008
P.O Boi 350
P.O Boi 14000
PO. Boi 3000
P O Boi 398704
9700 S Cats Avenue
2309 Renard Place. Suite 300
9700 SCass Avenue
RES/DRA NL/S-139
RES/DRANL/S-139
P O Boi 1970
P.O Bo< 1970
101 Marietta Si NS Suite 2900
26 Federal Pla a Room 906
3110 Port of Benton Blvd
P O Boi 999
9700 S Can Avenue
P O Boi 398704
10900 NE 8tb Street
P O Boi 1663 MS K490
P O Boi 398704
31 10 Port of Benton
26 Federal Pla a 2AWM-RAD
P.O Boi 162S
2790 Moiside Blvd
Mail Stop K490
P O Boi 999
Mail Stop 5-E-4
5310 Central Ave NE. Suite 1400
1445 Ross Avenue
773-41A
2309 Renard Place SE. Suite 300
2309 Renard Plice SE. Suite 300
2309 Renard Place SE. Suite 300
2309 Renard Place SE. Suite 300
7295 Highway 94 South
P O Boi 2008
P.O Boi 1970
401 M Streel.SW
841 Chestnut Bids
2597 B 3/4 Road
800 Oak Ridge Turnpike. PO Boi 350
75 Hawthorne Si
Miamisbia-g
Sterlms
Oak Ridge
Idaho Falb
Richland
Oak Ridse
Oak Ridse
Grsnd Junction
Miamisbirs
Cincinnati
Arjtonne
Albuquerque
Argonne
Washington
Washinston
Richland
Rich land
Atinta
NY
Richland
Richland
Arionne
Cincinnati
Bellevue
Lot Alamos
Cincinnati
Richland
New York
Idaho Falb
Monroe ville
Loi Alamoi
Albuquerque
Richland
Washington
Albuquerque
Dallas
Aiken
Albuquerque
Albuquerque
Albuquerque
Albuquerque
Si Charles
Oat Ridge
Rich land
Washington
Philadelphia
Grand Junction
Oak Ridge
San Fransisco
OH
VA
TN
ID
WA
TN
TN
CO
OH
OH
1L
NM
IL
DC
DC
WA
WA
GA
NY
WA
WA
IL
OH
WA
NM
OH
WA
NY
ID
PA
NM
NM
WA
DC
NM
TX
sc
NM
NM
NM
NM
MO
TN
WA
DC
PA
CO
TN
CA
4S343
22170
37830
8)415
99352
37831
37831
81502
45343
45239
60439
60439
20555
20555
99352
99352
30323
10278
99352
99352
60439
45239
98004
87545
45239
993S2
10278
83415
15146
87545
87185
99352
20555
87108
75202
29808
87106
87106
87106
87106
63303
37831
99352
20460
19107
81503
37831
94105
513-865-3936
208-526-4231
509-376-8410
615-576-2118
615-482-0347
303-248-6563
513-738-6200
708-972-4076
505-766-3061
972-3311
301 492 3999
301 492 3999
509-376-4436
509-376-7652
708-972- 3170
513-738-6200
206-451-4255
505-665- 1573
513-738-6200
509-374-8326
208-526-9039
509-375-2979
301-492-0578
505-845- 5671
214-655-7208
803-72S-5219
505-766-3047
505-766-3047
505-766-3047
505-766-3047
314-441-8086
615-576-2118
475-9633
303-248-6556
615-576-0463
NUREG-0707
FTWORK
MODFLOW/MOC
RSAC
CFEST
AIRDOS-EPA
RES RAD
GW Flow Model RESRAD
RES RAD
SWIFT III
ISCST/1SCLT
RAECOM
RADRSK AIRDOG
AIRDOS- PC DECHEM v 3 02 DECOM v 2 2 RES RAO
IMPACTS - BRC v 2 0 RAECOM MfcroAIRDOS v 2 0 GENII
MEPAS UNSAT-H v 2 0
PATHRAE-HAZPORFLO-3V1 0 PORFLO-3 v 2 0 PORMC-3 v 1 OPATHRAE-EPA
N/A
SUMO
MEPAS
CFEST
PATH
PRESTO-II SPUR GENII AIRO06-EPA PART61 BIOTRAN
OARTAB COMPLY AIRDOS
UNSAT-H
AIRDOS
FLASH/FLAME
STRIP IB SWIFT III GEOFLOW ODAST
TRACR3d
DCM3D INUSLT
ML CODE
RADON (RAECOM)
USGS-MOCUNSAT-2
ISCST SCREEN SIMS CHARM
PATHRAE DOSTOMAN
HEC-2 STEPH RAECOM SFRIPD UNSAT-2 BRUNZOG
PC- SLOPE HELP UTEXAS2 CONSOL SOIL
STABR HEC- 1 SBUHYD RETC F77 SFRIPE
STABLS
AIRDOS- EPA RAECOM RESRAD
AIRDO6-EPA
PHREEOE BALANCE
PRESTO-EPA-POP PRESTO-EPA-CPG
HEC- 1 HEC-2 RANDOM WALK
AIROOS- PC RESRAD COMPLY
3- d Mixing Cell SWIFT III MODFLOW
-------
TABLE 1 - Admnntratlve Data and Mode* Used
Count Name
Organization
Street Addrmi
City
State Zip
Telephone Mods to Used
45
«e
47
48
49
SO
51
52
53
MUcolm R Knapp
Robert Knowlton
FC Kcrntgay
Tin LeGcre
Herbert Lcvine
F Tom Liudsrom
F Tom Liudirom
Paul Mamnjly
Tim McCartm
Jere Millird
54 |S J Moirnon
55
56
57
58
i M
60
1 61
William E Murpbie
Robert Murphy
R L Mum
TE Mvrick
B A Napier
Jeff NefF
Eric Nicholi
621 FR O'Domell
1 F R O'Domell
63!N'aiaiieOlagne
64 1 Linda Pegues
65. JW Ray
68'LarrvG Reed
US NRC
US DOE/Envron Rest 772}
Wesnnghouse HanrcrdCo
EPA
SPS OWMD REECO INC
SPS DWMD REECO Inc
EGG Waste Mange menl
US NRC
Jacobs Engineer ins; Group
UNCCeotech
US DOE
Jacobs Engineer inn Croup
UNC Geotech
«7S Allendale Road
1000 Independence Ave
P O Box 2008
P O Box 1970
75 Hawthorne St
3281 S Highhnd
3281 S Huh land
200 Woodruff Avenue
5301 Central NE
P O Bo* 14000
EM -423
5301 Central Ave NE Suite MOO
P O Box 14000
Marim Mamella Energy Systems |PO Box 200' Bkg K-1037
Battelle- Northwest
USDOE
Weiss AuocialeslLLNLj
Oak Ridge National Lab
Oak Ridge National Lab
Wane Ma
Weston/Jacobs UMTRA Proj
Batlelle
P O Bo» 9«9
SOS King Avenue
5500 Shellmound Street
P O Box 2008
P O Box 2008
SNL
5301 Central Ave NE Suite 1700
King of Prussia
Washington
Oak Ridge
RKhland
San Francisco
Las Vegas
Las Vegas
Idaho Fall
Washington
Albuquerque
Grand Junction
Washington
Albuquerque
Grand Junction
OAk Ridge
Rich land
Columbus
Emeryville
Oak Ridge
Oak Ridge
Albuquerque
PA
DC
TN
WA
CA
NV
NV
ID
DC
NM
CO
DC
NM
CO
TN
WA
OH
CA
L TN
TN
NM
Albuquerque 1 NM
SOS KHIK Avenue • Columbus
EPA Office of ERR 1401 M SrreciSW 'Washington
67 1 Jon Richardi 1 USEPA Region 1 V
681 Paul Riltmann
69 1 Barry Roberts
70
71
l 7Z
73
74
75
76
' 77
1 78
79
BO
SI
82
83
84
C J Roberts
C J Roberli
C J Roberli
Rene R Rodriguez
Budhi Sagar
Sunn J Slidck
JohnL Snow
DwavneR Sneer
Robert Sienner
David J Thorne
Edward C Thorton
D Tomasko
Thomas J Walsh
k A Wiker
WJ Waugh
Victor L Weeks
R K White
R K While
1 R K While
85
86
87
R K While
W Alexander William
Steve Yabuiaki
Charley Yu
Westmghouse Hanford Co
EG&G Rocky Fbis Inc
West Valley Nuclear Svcs
West Valley Nuclear Svcs
West Valley Nuclear Svcs
Deconian and Decorum
Southwell Research Instil
OERR/OPM/KJ
Pacific Northwest Lab
WestmKhouse Hanford Co
Battelle- Northwest
UNC Geotech
Wesunghouse Hanford Co
Argonne National Lab
Feed Materials Prod Ctr
Oak Ridge National Lab
UNC Geotech
EPAIV/WaiteMngRCRA FedFac
Martin Marietta
Martin Mametra Enemy Svitems
Martin Mamella Energy Syslemi
Marlm Mamelta Energ* Syslemi
US DOE
Paellic Northwett Lab
Argonne National Lab
4291 East Meadow Dr
P O Box 1970
P O BOX 464 Trailer TI30B EMAD
P O Box 191
P O Box 191
P O Box 191
P O Box 1625
6220 Culebra Road
Waterside Mall
P O Box 999
PO Box 1970 MSINR2-77
PO Box 999
2597 B 3/4 Road
P O Box 1970
9700 S Can Avenue
P O Box 39S704
P O Box 2008
P O Box 14000
34$ Courtland St. N E
P O Box 2008 ORNL
P O Box 2008.ORNL
P O Box 2008. ORNL
PO Box 2008. ORNL
EM-421
PO Box 998
9700 SCaia Avenue
Duluth
RKhland
Golden
West Valky
Wesi Valley
West Valley
Idaho Falls
San Antonio
Washington
Richland
RKhland
RKhland
Grand Junction
Richland
Argonne
Cincinnati
Oak Ridge
Grand Junction
Alanta
Oak Ridge
Oak Ridge
OH
DC
GA
WA
CO
NY
NY
NY
ID
TX
DC
WA
WA
WA
CO
WA
IL
OH
TN
CO
GA
TN
TN
Oak Ridge > TN
Oak Ridne
Washington
Richland
Argonne
TN
DC
WA
IL
19406
20S85
37831
99)52
941 OS
89109
89109
83415
20SS5
87108
81502
20S4S
87108
81502
17831
99352
43201
94608
37831
37831
87185
87108
43201
:0466
30136
99352
80402
14171
14171
14171
83401
7822S
20460
99152
99352
99352
81S03
99352
60439
45239
37831
81502
303*5
37831
37831
37831
37831
20585
99352
60439
615- S74- 5776
509-376-1225
505-845-5700
303-248-6373
301-353-5896
505-845-5713
303-248-64)24
61S-574-395J
509-375-3896
614-424-3090
615-576-2132
615-576- 2132
S05-84S-4030
6N-429 -SS22
404-347-3907
509-376-8191
716-142- 4271
716-942-4271
716-942-4271
526-8078
509-376-1352
509-373-1382
509-375-2916
303-248-6749
708-972-3170
513-738-6200
615-S74-4432
303-248-6431
509-376-3290
708-972-5589
RES RAD ,
MESOI |
VAM2O
MOOFLOW FLOWPATH CFEST
TDRECH23 GCDT3DH3 ODRECH6 TDRECH2I CASCADER
TDRECH11 GCDT3DH4 OORECH7 GCOT3DH5TDRECHI2
PAGAN TRACR3D
OCM3O TOUGH NEFTRAN II DPCT SWIFT h
DECHEM
HYDROGEOCHEM
RESRAD
LTSAMP
RESRAD
BARRIER USGS-MOC UTM
DfTTY ONSfTEAflAXI GENII
AIROOS RESRAO
CFEST
DOSES CAP-88 MACCS AIROOS- EPA
CONDOS-II GCST/SCLT RASCAL, v 1 3
NEFTRAN II
HELP ver 2 02 UNSAT-H, ver 1 1 STABl UNSAT-2 1 RETC F77
RESRAD
SWIFT II MO03D IMPACT PATHRAE
GENII AIROOS -PC
VAM2d TARGET MOOFLOW MOC
MINTED RESRAO PHREEOE I5OSHLD HELP
MILDOS AFTOX PLASM MODFLO AIRDOS-PC
PATHHAE-EPA INPUFF COMPLY MAXI1
RESRAO
DfTTY
CFEST PORFLO-3V 10
ARO.
RHFS-LCHRS-I
MICIO AIROOS
MINTED EQ3/6
CFEST
ISCSTHARM-II
USGS-MOC
RAECOM
HELP PATH RAY RAO PATH -RAY HAZ FT WORK
RESRAD Bechtel proprietary SOURCE 2 MEPAS
MT3O HELP CREAMS SOLUTE
MOOFLOW NEWBOX. FLOWTHROUGH CYLSEC SWIFT Rock-are & SURFER
SEFTRAN HSPF PATHRBK MOC THEM
RESRAD '
TEMPEST/FLESCOT
MAT123D RESRAD PRESTO-EPA UDAD MILDOS-AREA
-------
TABLE 2 - Alphabetical List of Models, Model Types and References
16-Mar-93
MODEL
3d Mixing Cell
AFTOX
AIRDOS(-EPA.-PC)
ARCL
BALANCE
BARRIER
Bechtel Proprietary
BIOTRAN
BRUNZOG
CAP -88
CASCADER
CFEST
CHARM
COMPLY
CONOOS-II
CONSOL
CREAMS
CYLSEC
DARTAB
DCM3D
DECHEM
DECOM
DITTY
DOSES
DOSTOMAN
DPCT
EQ3/6
FLASH/FLAME
FLOWPATH
FLOWTHROUGH
FT WORK
GCDT3DH
GENII
GENMOD
GEOFLOW
GW FLOW
HARM- II
HEC-1.-2
M
u
1
t
i
M
•
d
I
a
•
•
•
•
•
•
A
i
r
•
•
•
•
•
•
•
•
•
S
u
r
f
W
•
1
a
r
a
a
G
r
n
d
M
a
1
a
r
a
a
a
a
a
a
a
a
a
Q
a
0
c
h
a
IT
1
C
•
1
a
a
E
n
0
P
a
r
f
a
r
n
a
a
a
a
S
c
r
a
a
n
i
n
g
a
D
a
t
a
i
e
d
a
a
a
a
a
a
a
R
a
d
M
a
t
a
r
a
a
a
a
a
a
a
a
a
a
a
a
a
a
a
a
Reference 1
U.S. Army. 19xx
Moore etal.. 1979
Napier & Piepel. 1988
Parkhurst et al . 1982
Shuman etal., 1989
Bechtel Corporation, 19xx
Gallegar etal , 1980
Chamberlain, 19xx
see AIRDOS
Gupta etal., 1982
USEPA, 19xx
USEPA. 1989
USNRC, 19xx
U.C.Berkeley. 19xx
Knisel. 1980
Begovich etal., 1981
.
Radiological Assessment Corp , 19xx
Napier etal. 1986
ORNL. 19xx
Root. 1981
Schwartz & Crowe, 1980
Wolery & Walters, 1975
Napier etal. 1988
Atomic Energy of Canada, 19xx
D'Appolonia Consulting Eng., 1980
Natural Sci. & Eng. Counc., Canada
U S. Army Corps of Eng.. 1981
Reference 2
Till etal. 1987
Gupta etal . 1987
King etal.. 1985
Schwartz, 1978
Wolery etal.. 1988
U S Army Corps of Eng , 1982
Reference 3
U.S EPA. 19xx
Delaney, 1986
-------
TABLE 2 - Alphabetical List of Models. Model Types and References
16-Mar-93
MODEL
HELP
HRS-1
HSPF
HYDROGEOCHEM
IMPACTS (PART61) I-BRC
INPUFF
ISCST/ISCLT
ISOSHLD(-II)
LTSAMP
MACCS
MAT123D
MEPAS
MESOI
MILDOS(-AREA)
MINTED (-A1.-A2)
ML CODE
MOC
MOD3D
MODFLOW
MT3D
N EFT RAN II
NEWBOX
NUREG-0707
ODAST
ODRECH6.7
ONSITE/MAXI1
PAGAN
IPATH
PATHRAE EPA. HA2. RAD
PATHRISK
PC-SLOPE
IPHREEQE
[PLASM
PORFLO-3
PORMC-3
PRESTO-II EPA.CPG.POP
M
u
t
i
M
a
d
i
a
a
•
•
a
a
a
a
A
i
r
a
a
a
a
a
S
u
r
1
M
•
1
a
r
a
a
G
r
n
d
W
a
t
a
r
a
a
a
a
a
G
a
o
G
h
a
IT
1
G
•
1
a
a
a
E
n
a
p
a
r
f
o
r
m
a
a
a
a
a
a
a
S
c
r
a
a
n
i
n
a
a
a
a
a
D
a
t
a
i
1
a
d
a
a
a
R
a
d
M
a
t
a
r
a
a
a
a
a
a
a
a
a
a
a
a
a
a
a
a
a
Reference 1
Schroeder et al . 1 984
Stenner etal., 1986
Johanson et al . 1984
Yeh &Tripathi. 1&xx
Oztunah etal . 1986
Peterson & Lavdas. 1986
Bowers etal., 1979
Engleetal, 1966
Jacobs Engineering, 19xx
Sandia National Lab., 19xx
Yu, 19xx
Droppo etal., 1989
Ramsdell. et al , 1983
Strenge and Bander. 1981
Krupka & Morrey, 1985
Napier, 19xx
Konikow & Bredehoeft. 1978
McDonald & Harbough, 1984
McDonald & Harbough, 1989
Zheng. C. 1990
Longsine, Bonano & Harlan, 1987
Eckerman & Young, 19xx
Javendal etal. 1984
Napier et al . 1 984
Kozak etal , 1990a
Lee. 19xx
Rogers & Hmz, 1987
Geo- Slope, Inc , 19xx
Parkhurst etal , 1980
Pnckett & Lonnquist, 1971
Runchal & Sagar. 1985
Analytic & Comput Res , Inc , 19xx
Fields etal. 1986
Reference 2
Oztunali & Roles. 1986
General Sciences Corp , 1986
TRC Environmental Cons , Inc , 19xx
Sumnar etal., 1967
Doctor etal , 1990
Yuan etal., 1989
Allison et al.. 1990
Kennedy etal . 1986
Rogers & Hmz. 1987
Reference 3
TRC Environmental Cons . Inc . 1988
Whelan etal. 1987
Peterson etal., 1987
1
;
Fields etal 1897a.b
-------
TABLE 2 - Alphabetical List of Models. Model Types and References
16-Mar-93
MODEL
RAECOM
RADRISK
RANDOM WALK
RASCAL
RESRAD
RETC F77
RHRS-LC
RSAC-3
SBUHYD
SCREEN
SEFTRAN
SFRIPE
SIMS
SOIL
SOLLfTE
SOURCE 2
SPUR
STABL. STABL5
STABR
STEPH
STRIP IB
SUMO
SWIFT (ll.lll)
TARGET
TDRECH
TEMPEST/FLESCOT
THEM
TOUGH
TRACR3D
UDAD
UNSAT-2(-H)
UTEXAS2
UTM
VAM2D (-3D)
M
u
1
I
I
M
a
d
i
a
a
a
a
a
a
a
a
a
A
i
r
a
a
a
a
a
S
u
r
f
W
•
I
a
r
a
a
Q
r
n
d
W
a
t
a
r
a
a
a
a
a
a
a
a
a
a
O
a
o
c
h
a
in
c
a
1
E
n
g
p
a
r
f
o
r
n
a
a
a
a
a
a
a
S
c
r
e
a
n
i
n
g
a
a
D
a
t
a
i
a
d
a
a
a
a
a
R
a
d
H
a
1
a
r
a
a
a
a
a
a
a
a
a
a
a
a
a
Reference 1 Reference 2 Reference 3
Rogers et al.. 1984
Dunning et al., 1980
Prickett et al., 1981
ORNL & Phoenix Associates, 19xx
Gilbert et al . 1988
Mualem, 1976
Stenner et al.. 1986
Wenzel. 1982
Stubenhaer. 1975
USEPA. 19xx
MK Environmental, 19xx
USEPA. 19xx
El -Kadi. 1985
USEPA. 19xx
Siegel. I9xx
U.C Berkeley. 19xx
MK Environmental, 19xx
USDOE, 19xx
Reeve s et al , 1986
Trent et al . 1983
Pruess & Wang, 1984
Travis et al.. 1984
Momenietal. 1979
Davis & Neuman, 1983
Wright. 19xx
Luxmore & Huff. 1989
Huyakornet al . 1989
U.S DOT & Purdue Univ.. 19xx
Reeves & Cromwell. 1981
Omshi. Trent & Klontz, 1985
Pruess, 1986
.
Payer et al . 1986
Huyakorn. 19xx
Ward. Reeves & Duda, 1984
Trent & Onishi, 1989
N>
-------
Tables-Model. Site Type.Contaminant. Endpoht. Effort.Validation. Publication
Count
1
2
3
4
5
a
7
8
9
10
11
12
13
14
15
18
17
18
19
20
21
22
23
24
25
MODEL
3-d Mtxha Cell
AFTOX
AIRDCG
AIRDOS
AIRD06
AIROQB
AIRDOS-EPA
AIRDOS-EPA
AIRDOS-EPA
AIRO06-PC
Al ROCS-PC
AIRDOS-PC
AIRD06-PC
ARCL
BALANCE
BARRIER
Bechtel propreiary
BIOTRAN
BRUNZOG
CAP -88
CASCADED
CFEST
CFEST
CFEST
CFEST
CFEST.
CHARM
COMPLY
COMPLY
COMPLY
CONDOS-II
CONSOL
CREAMS
CYLSEC
OARTAB
OARTAB
DCM3O
DCM3D
OECHEM
OECHEM V3O2
OECOM v 2 2
DITTY
DfTTY
DOSES
OOSTOMAN
SITE TYPE
EPA Suoarfund
DOE
DOE Defense
DOE National Laboratory
SFMP
DOE Oetenie
EPASuoerfund
Federal Facility
DOE Defense
FUSRAP
DOE Oefenae
NRC
OOE
SFMP
OOE Defame
DOE Defense
EPA Superfund
OOE National Laboratory
UMTRA
Federal Facility
OOE Defense
DOE Defense
DOE Defense
EPA CERCLA NPL DOE NatlLb
SFMP. Superfund
EPA Superfund
EPA Superfund
OOE
FUSRAP
DOE Defense
Federal Facility
UMTRA
EPA Superfund
EPASuperfund
DOE Defense
DOE Defense
UMTRA
DOE NRC
NRC
NRC H-L Waste repository
OOE Defense
Federal Facility
DOE Defense
CONTAMINANT
voe's
non radloloaic
radionuclldes
radionuclides
Pu.Co. Am.U.CS
all natural series Isotopes
radlonuclldea
alkaline earths, actinldes. etc
radionuclldes
U-238 and Th-232 decay chains
41 radlonuclidei
see namual
non radloloaic
nat. enr U. transuranlcs. fission
radionuclldes
NA
radionuclldes
Tritium and Radon
Chlorinated allphatlcs. Tritium
tritium, U
U-238. Th-232. metals, nltroaromat
tritium, uranium
participate! , vocs
radionuclldes
radionuclldes
U-238 and Th-232 decay chains
radionuclldes
NA
NA-Water Balance
All radlonuclidei
U-234. U-239. U-238. U-238.
radionuclldes
Hlghlevel waste radionuclides
As.Se. V. U. Mo. Pb. limited orgs
U.Th.Ra,As
U.Th.Ra
more ttian 250 radionuclides
Radlosotopes-lodineneotuniun etc
radionuclides
PU-23B.Pu-239.Cs-137,Sr-90.3H.
ENDPONT
environmental concentration
environmental concentration
effective dose-eaurvalent
dose commitment
dose commitment
dose commitment
env cone and dose commitment
dose commitment, rak
env cone . comm eft dose eo. risk
effective dose equivalent
dose commitment
dose commitment
dose commitment
max allowable residual levels
env cone In aqueous systems
dose
env cone . comm eft dose eq, risk
depth of thaw penetration
env cone . dose-eq. rck
environmental concentrations
environmental concentration
environmental concentration
environmental concentration
concentration
env cone . risk assessment
dose commitment
dose commitment
air. food cone . dose from oblects
calculates settlement
Percent Runoff. Evaporation. Infiltration etc
Concentrations
dose commitment
dose commitment
hydrollc flow/Integrated discharge
soil, cw cone , risk (see note)
reference value
concentration, doses
individual and population doses
dose commitment
dose
dose commitment
EFFORT
unknown
as needed
9 mm/vr
4 mm
S- 12 mm/vr
6 mm
24-36mm nt
as needed
as needed
1mm
1 FTE/yr
none
Bmy/yr
24-36mm nt
3
36mm
6mm. 8mm
12mm
15 my
variable
•* needed
3-4 mm
1mm
05
OSmm/Update
4 mm
4mm
12 mm
3900 + 900
as needed
i
several my
2-emm
2
24 mm
V/C'
YES
NO
NO
YES
NO
NO
NO
YES
NO
NO
NO
NO
NO
NO
YES
NO
NO
YES
NO
NO
NO
YES
NO
NO
NO
NO
NO
YES
YES
YES
NO
NO
NO
NO
NO
NO
NO
PUBLICATION
NO
YES ANL-E env reoorti
NO
NO
NO
NO
NO
NO
NO
NO
NO
NO
YES LLNL 1991
YES WHC-EP-OI33.PNL-S3I5-2
NO
NO
NO
NO
YES Bechtel Proprietary Documents
NO
NO
NO
NO
YESDOE/ES-0113
NO
NAME 1
EUzatxtnKdtfw 1
CJ Roberto
Man Penman '
OwtML Crwever
David E Fsni j
JetlNifl
BobHUvac*
F O HofthwB O ainuxt
MacEnni i
On line Daly
CJ Roe.ru
MarfcE Kfr*
PaulRMnann
DwnneR Se»er
J 0 Hoover
TE Mycltx
RK Win
MacEnm
Marvin W Henohrion
FR ODonnen i
F Tom UucWofn 1
EncNIehoii
JohnLSmoot ,
Ljsa A DirrwuD Tomxko
Marcel P Beroerran
Herbert LMne '
MarkHaman
C J Rob.rn ,
OavldE Farti
Ma*E Key. j
FR ODemll
Martin W Honkrien 1
RK WHk j
RK WM.
Owiae F«n»
OoidE Fans j
OaXaQalleoBi 1
Ttm McCann |
Or Jsre Mina-d
CrnmneOaly
Crrlslne Daly
BANapw
Or BuotiSaor |
FR OOornen 1
JornHasMow
I-J
to
-------
Table 3-Moael. Site Typa.Contunlnu», Endpont, Efloft, Validation. Publication
2ount
26
27
28
29
30
31
32
34
35
36
37
38
38
40
41
42
43
44
45
46
47
4B
49
SO
SI
52
S3
54
55
50
vlOOEL
3PCT
EOV8
FLASH/FLAME
FLOWPATH
FTWORK
FTWORK
GCDT3DH3
GCDT3DH4
GENII
GENII
GENII
GENII
GENII
GENNMOO
GEOFLOW
GW Flow Model
HARM -II
HEC-1
HEC-1
HEC-2
HEC-2
HELP
HELP
HELP
HELP
HELP ver 2 02
HRS-I
HSPF
HYDHOGEOCHEM
IMPACT
IMPACTS -BHCv 20
INPUFF
INU5LT
ISCST
ISCST
ISCST/ISCLT
ISCST/ISCLT
ISOSHLD
LTSAMP
MACCS
MAT123D
MAX!
MEPAS
MEPAS
MEPAS
MESOI
Micro AIROO9
MIcrcAIROOS v 2 0
SITE TYPE
DOE Defense
EPA Supertund
EPA Supertund
EPA Supertund Savannah Rv
EPA Supertund (DOE)
DOE Defense
DOE Defense
DOE DefenseSFMP
DOE National Laboratory
DOE Defense
DOE.NRC
DOE Defense
DOE Defense
DOE Defense
Federal Facility
DOE Defense
UMTHA
OOE.DOE Defenoe.SFMP.SF
UMTRA
DOE.DOE Defense.SFMP.SF
DOE
EPA Supertund
UMTRA
EPASuperfund — DOESavann
UMTRA
EPA Supertund
EPA Sunerfund
DOE. NE. DP
EPA Suoertund
NRC
DOE
GW
EPASuperfund
DOE Defense
SFMP
Federal Facility
DOE
UMTRA
Federal Facility
FUSRAP/SFMP
DOE
EPA Suoertund. DOE Defence
Rankho model for CERCLA
DOE Defense
Federal Facility
NRC
CONTAMINANT
Sr-BO
radlofiuclldes and nonradloloalc
lead, mercury, nitrate,
30 contain Inanti of concern
Tritium and Radon
Tritium and Radon
more than 290 radlonuclldes
any related to decommotionino
radlonuclldea
radian uclldes
24O radlonuclldes
radionucllda
How
U-234, various liquids and gasaa
U. VOC's. toxic metals, aromatics
How
U. VOC's. toxic metals, aromatic*
now
now
tatrachloroethylene
radlonuclldes and nonradlologlc
All contaminants
to be determined. U likely
H-3. C-14. Co-80. Sr-90. bee note)
any In library
non radlologte
particuiates. vocs
S02
rad, nonrad and generic releases
PMIOandTSP
radlonuclldea
partjculalei. radon
fission product*
U. radlum-226
radlonuclldas
76 rads. 318 nonradletogte
radlonuclldea and nonradlofoglc
toxic gases
U.Th.Ra
ENDPOMT
concentration
env cone . Che Interaction water/soil
environmental concentration
concentration
constituent consenbatons
environmental concentration RA
environmental concentrations
environment11' concentrations
cone . dose.dose comm. Integ dose
dose
dose commitment
env cone . comm eft dose eq. risk
env cone . dose commitment
Internal doslmetry
gw flux
environmental concentration
env cone
water levels and flow rates
environmental concentration
water levels, flow rates end veloc
rscharge and discharge rats*
constituent consentratlons
MRS scores
Time series of contaminant passing a point
to be determined
70 year short-term doss eg
dose
environmental concentration
env cone , risk assessment
environmental concentration
around-level air cone
lono/shoit term env cone
external dose and dose rates
cone at receptor locations
env cone , doie-eq, rak
cone In ground water
dose commitment
env cone . dose comm. risk factors
dose, hazard Index, risk
short-term ground level cone
env cone . dose commitment, uptake
dose
EFFORT
6mm
see note
36 mm
6 MM
12 mm
> 5 my
1mm
unknown
24-38mm nt
5FTE/yr
30 mm
2 years ax
3 man— yrs
8 mm note
6 mm note
as needed
6MM
24mm
13mm
to be dot
unknown
2 mm
as needed
variable
unknown
OS
5 mm
as needed
unknown
2
6 mm
as needed
$500.000
2 years
0
unknown
1mm
VIC*
YES
NO
NO
NO
YES
NO
NO
YES
NO
NO
YES
NO
NO
YES
NO
YES
NO
NO
NO
NO
NO
NO
YES
NO
NO
NO
YES
NO
NO
NO
NO
NO
NO
YES
NO
YES
YES
YES
NO
PUBLICATION
NO
NO
NO
NO
NO
YES reports to SRS
YES PNL-6625. DOE/ES-01190
NO
YES
NO
NO
NO
NO
NO
YES AML symposium, 1868
YES
YES AML symposium, 1888
YES
YES
NO
YES PNL-6456
NO
NO
NO
NO
NO
NO
NO
YES UMTRA Env Assessments
YES
YESPNL-7102.SF-8B
YES Whelan et al
YES
NO
NO
NAME
TrnMcCarsn
Or Edward C Thorton
Joe Frailer
Herbert L»vtne
Victor L Weeks
P«t«rF Anderson
FTomliudstom
FTomUudsrom
BA Near
CrrMneO«y
Or Roy Eckert
MecEmi
PeJRitmem
Or RorEdon
asryOaUM
LS C*n
Themes J WePtfi
MerkKeuteXy
Marvin W H«nder»on
MerkKeuteky
Marvin W Henomon
CJ Roberts
MenkiW Henaereon
R 1C White
Victor L weeks
UndaPeojes
Robert Stunrar
R K WMto
SJ Morrison
Jon Richards
Chrlstne Dally
CJ Roberts
David (Me got
MarkHansen
Thorns J Wifflsh
FR OOomeO
Youno- Soo Chano
CJ Roberts
Robert Murphy
FR Doomed
Or Oerley Yu
CJ Robert!
Or Jernet O Oroppo Jr
Or JerryO Oevls
RK White
FC Kemegey
DavWJ Thome
CrtlslneDeny
-------
Table 3-Model, SrUTypo.Contamlnant. Endporit. Effort. Validation, Publication
W-OCT-B
Count
57
98
98
60
61
62
83
64
63
88
87
68
69
70
71
72
73
74
75
76
77
78
78
80
81
82
83
84
85
MODEL
MILOOS
MILOOS-AREA
MINTED
MINTED
ML CODE
MOC
MOC
MO03D
MOOFLOW
MOOFLOW
MOOFLOW
MODFLOW
MOOFLOW
MOOFLOW/MOC
MT30
MEFTHAN II
MEFTHAN II
MEWBOX. Flowthrough
MUREG-0707
OOAST
OORECH6
ODRECH7
ONSITE/MAXI
ONSITE/MAXI 1
PAGAN
PAHT61
PATH
Path Ray Rad
PATHRAE
PATHRAE
PATHRAE- EPA
PATHRAE-EPA
PATMRAE-HAZ
PATHRAE-HAZ
PATH RISK
PC -SLOPE
PHREEOE
PHREEQE
PLASM
PORFLO-3 v 1 0
PORFLO-3V10
PORMC-3V10
PORFLO-3 v 20
PRESTO- EPA
PHESTO-EPA-CPG
PHESTO-EPA-POP
PRESTO-II
RADON (RAECOM)
RAOnSK
RAECOM
SITE TYPE
DOE
FUSRAPSFMP
DOE Defense
DOE
DOE Defense
OOE Defense
Perfromanee Aiinimant
OOE Defense
OOE
EPASuperfund
DOE Defense
EPASuperfund
EPASupeffund
EPASuperfund
EPASuperfund
DOENRC
Performance Assesment
DOE
DOE Defense
DOE Defense
DOE Defense
DOE Delense.SFMP.FUSRAP
DOE Defense
OOE
DOE National Laboratory
FUSRAP
EPA Suparfund Savannah Rv
OOE Defense
DOE Defense
DOE
DOE Defense
OOE Defense
EPASuperfund
UMTRA
DOE
OOE Defense
DOE
DOE Defense
DOE Defense
DOE Defense
DOE Defense
FUSRAP
Generic
Generic
DOE National laboratory
UMTRA
OOE National Laboratory
OOE NRC
UMTRA
CONTAMINANT
radian uclldes
Urankim series liotooes
nonradlologlc
lodria-131
VOC's
All contaminants
radlonuclldea
flow
VOC'S
All contaminants and radionuclldes
nuclide* 1 10 CFR Part SO
Most radloaotopas
rads and selected nonrads
Tritium and Radon
Trltfum and Radon
more than 250 radionuclldes
radlonuclldes
Radioetotopes and nonradiologlc
radlonuclldas
Co- 80.Cs- 137. Sb- 129. europium- 1
trrflu m .radtim .ceslu m .strontium .
see DPST-B6-291
radlonuelldas
radionuclldes
radionuclldes
hazardous chemicals
aresnic, barium, cadmium, chromium,
All radlonuclldes
NA
non radiologlc
Dow
radlonuclldes and nonradlologlc
at users discretion
radlonuclldes and nonradlologlc
radlonuclldes and nonradiologlc
Ra-228
40 rads commonly found in llw
40 radi commonly found in llw
radionuclldes
Radon -222
all natural series Isotopes
ENDPONT
dose commitment
env cone . che Interaction water/soil
dose commitment
oroundwatar concentration
environmental concentration
water levels
environmental concentration
concentration
Flow Rates
Concentration and travel time
cumalattve curles/specboundApectlmo
Integrated daeharge
concentration and dose
dose commitment
environmental concentrations
environmental concentrations
env cone , Indiv max annual dose
dose commitment
environmental concentration
env cone , comm eff dose eg. risk
dose commitment
constituent concentrations
dose commitment
dose
dose commitment
dose
hazard Index, mk
constituent concentrations
Dose
failure surfaces . factors of safety
env cone in agueous systems
heat.gw/conl flux, cone 1 .2.3-0
env cone
heat.gw/conl flux, cone 1.2,3-D
heat.gw/conl flux, cone 1.2.3-D
dose commitment
dose commitment, fatal health eff
dose commitment, fatal health eff
env cone . comm eff dose eg. risk
surface radon flux
dose commitment
env eonc and dose commitment
EFFORT
as needed
12 mm
as needed
see note
12mm
5mm
Ongoing effort
as needed
3mm
unknown
12 mm
6mm
8 mm
6mm
several my
unknown
several
24-36mm nt
4mm + 6mm
6 MM
48 mm
as needed
unknown
unknown
a MM
8 mm
as needed
none
as needed
3FTE.+3mm
6 mm
6 mm 1890
8 mm 1990
1 mm
4 my. dev
4 my. dev
24-36mmnt
3— 5mm NRC
5 mm/yr
6mm
v/c-
HO
YES
MO
MO
NO
YES
NO
NO
NO
YES
NO
NO
NO
NO
NO
NO
NO
YES
NO
NO
NO
NO
NO
NO
NO
NO
NO
NO
NO
YES
YES
NO
YES
YES
YES
YES
NO
NO
NO
NO
PUBLICATION
YES ANL/ES-181
NO
NO
NO
NO
NO
NO
NO
YES
YES NUREG-0707
YESOOE/EB-0113
YES
NO
NO
NO
NO
YES SRL-EIS on llw
YES SRL ES on trw sites
NO
YES ORNUER/Sub-67/9eoS3/S/V3-V6
NO
NO
YESSmootandSagar 1990
YESPNL-7221
YES Conference proceedings
YES
YES
NO
YES NUREG/CR-3533
YES ANL-E env reports
NO
NAME
CJBob.rH
Or ChartayYu
CJ Retorts
Or Eoward C TrxTtan
WchardO autxn
Bary Rabam
* 1C write
JonHctwat
CJ RoDafts
BaiyRebam
Efeabeth Kelchar
H«t>artLs»lne
Richard W A-nMti
RKVttiw
Matte cugne
TknMcCann
fl 1C Wfttts)
OmM Abbot
OaryOillo!
FTamUuairorn
F Tom Uudstom
BANsaer
Dr RovEdcert
PBJManncJy
MacEnnrs
KjrawSiJ Eoar
Victor L Weeks
JohnHaulow
JonRicharOB
CJ Bob.rn
Dr JirryD Oawli
Dr JerryD Davit
victor L Wseki
RK Whta
M«rjn W Hvxkrun
CJ Rctord
J O Heonr
CJ ROMRS
Dr JaryO Oavii
JomL Srnoot
Or JnyO Oawii
Or J«rvO Oavii
Dr ChalayYu
Chang y«no Huio
Chang rang Hung
MacEmi
QiorgioN Qnugnoll
OwlnLChMMr
eobHIavacak
-------
Table 3-Model, SiteType.Contamlnant. Endpont. Effort. Validation, Publication
30-OCT-B1
Count
B6
87
88
89
90
91
92
94
99
96
87
98
99
100
101
102
103
104
105
108
107
108
109
MODEL
RAECOM
RAECOM
RAECOM
RAECOM
RANDOM WALK
RASCAL, vU
RESRAD
RESRAD
RESRAD
RESRAD
RESRAD
RESRAD
RESRAD
RESRAD
RESRAO
RESRAD
RESRAD
RESRAO
RESRAO
RESRAO
RESRAO
RESRAO
RESRAO
RESRAD
RESRAD •
RETC F77
RETC F77
RHRS-LC
Rockware & SURFER
RSAC
SCREEN
SEFTRAN
SFRIPE
SFRIPE
SIMS
SOIL
SOLUTE
SOURCE 2
SPUR
STABL
STABLS
STABR
STEPH
Strip IB
SUMO
SWIFT
SWIFT II
SWIFT II
SWIFT III
SITE TYPE
EPASuoeriund
SFMP
UMTRA
DOE.DOE Defeme.SFMP.SF
Federal Facility
DOE Oefenie
SFMP
DOE Futrap
FUSRAP
FUSRAPfiFMP
SFMP
SFMP/FUSRAP
DOE FUSRAP
DOE
DOE. NRC
SFMP
DOE Detente
EPASupertund
SFMP
DOE Detente
DOE Defense
SFMP
DOE Detente
EPASupertund
EPA Supertund
UMTRA
UMTRA
EPASuperfund
EPA Supertund
INEL
EPA Supertund
Performance Ateettment
UMTRA
UMTRA
EPASuperfund
UMTRA
EPASupertund
EPASuperfund
DOE National Laboratory
UMTRA
UMTRA
UMTRA
UMTRA
DOE Detente
EPA Superfund Porkmouth
DOE Detente
DOE Detente
CONTAMINANT
Ra
Ra-226
radon
Radon -222
U.VOC't, toxic metalt, aromatlct
reactor (flttlon product) rads
U.Th.Ra.Co
Site epecfflc radlOBtopet
all natural terlee Isotopes
radionuelides
Pu-23S.Th
Pu-238,Th
U,Cs-137
radlonuclldes
Pu, Co. Am. U. CS, RCRA Hal. PCBs
Ct, U, CO, Pu, Am
U-238. U-234. Th-230
U-238 and Th-232 decay chains
Co-60. Ct-137
All radlonuclldes and decay products
U-238. U-234. Th-230
U-238. U-234. Th-230
40 Isotopes. 38 daughters
radlonuclldes
RadlOBOtopet - D&D
NA
radlonuclldes and nonradlologie
radlonuclldes
partjculatet. voce
NA
NA
partlculates. vocs
Radlonuclldes
radlonuclldes
NA
NA
NA
tranturanict. flstlon products
radlonuclldes
uranium, others as necessary
ENOPONT
concentratlonynux
estimated Interior WLe
radon fluxes and concentrations
radon emanation from toll
environmental concentration
acute/long term dote-eg. health eff
concentration
dose
env cone and dose commitment
dose com mrtment
dose commitment
dose commitment
dose commitment
dose commitment
dose commitment
dose
soil cone - cleanup guidelines
dose commitment
dose
guldelkie values lor radlcnuclldet
toll cone - cleanup guidelines
soil cone - cleanup guidelines
eff and comm eff dote equivalent
dose com mrtment
dote commitments, clean up guides
hydraulic pars of partial sat tolls
reviled hazard rankhg tyttem score
Cl/m2. photon flux, exp, dose.ede
env cone . risk assessment
factor of safety for riprap sizing
factor of safely for riprap sizing
env cone , risk assessment
hydraulic oars of part saturat soil
Cocentratlon
env cone , com m efl dose eq. risk
failure surfaces , factors of safety
failure surfaces , factors of safety
riprap sizing
env cone . dose, health effects
environmental concentration
ground water flow
cone at offslte receptors
EFFORT
3 mm
1mm
8 mm note
0
as needed
3 m-m
6mm
as needed
20 mm
unknown
B— 12 mm/vr
mm
mm
mm
mm
mm
as needed
Y
6-10 mm
3mm 1990
variable
variable
Smm/updates
24-38mm nt
36 mm
6 mm
150 + 50
V/C*
YES
NO
HO
MO
YES
MO
MO
YES
MO
NO
MO
NO
YES
YES
NO
NO
NO
YES
NO
NO
NO
YES
YES
NO
NO
NO
YES
NO
NO
YES
NO
YES
NO
NO
NO
NO
NO
NO
YES
YES
PUBLICATION
NO
NO
YES
MO
YES AMI symposium. 1989
MO
MO
MO
NO
YES Internal Repons
YES ANL/ES- 1 60, DOE/CH 890 1
NO
NO
NO
NO
NO
NO
NO
YES
YES
NO
YES
NO
NO
NO
NO
YES
YES Bechtel proprietary documents
NO
NO
NO
NO
YES NUREG 1249 Hydrocoln
YES draft 6/90
NAME
CrrMmDinv
OHM A. exertion
NUnlnW Henekrion
WJ Wkugn
MrtKauMcy
Ffl OQonmO
CMitneOelv
Robert ttvwlton
B«* Hlevx^ik
CJ Roberta
JeririQ Cationo
DanMQ Cjrtxno
Dr OwrleyYu
Or Hoy EoXrt
JiflNefl
JW H«y
LS dm
MvKE Kw«
ReneR RodrtguM
RK. w>it«
RL Murr!
ILMurt
VMHam C Bordcn
WIumE MurpHe
W Meundir WUUerm
UndaPeojet
Mmfn W HcndeTMn
Robert Sterner
RlCVtttte
Burton R Bddrtn
MwkHiTMn
RK. WNte
MmlnW Herdrion
ManftiW Hendnon
MatcHeraen
MnlnW Hmckrun
RK.VWite
RK WNt>
MecEnrti
UndsPecvei
MsrtlnW Herxftrion
MnlnW Herdrion
M«-*iW Hwxkrion
OeryaelUol
PO Doctor
RK WNte
JonRlervroi
Tim McCenn
Oerrii J Car
-------
Table 3-Modal. Sit* Type.Contamlnant, EndpoM. Effort. Validation. Publication
Count
110
111
112
113
114
115
118
117
118
119
120
121
122
123
124
12S
126
127
•V/C"*
MODEL
SWIFT III
SWIFT III
TARGET
TORECHH
TDRECH12
TDRECH21
TDRECH23
TEMPEST/FLESCOT
THEM
TOUCH
TRACR3O
TRACR3O
UDAO
UNSAT-2
UNSAT-2
UNSAT-2 1
UNSAT-H
UNSAT-H v 2 0
UNSAT-H. ver 1 1
USGS-MOC
USGS-MOC
USGS-MOC
USQS-MOC
UTEXAS2
UTM
UTM
VAM2D
VAM20
SITE TYPE
EPASuparfund
DOE Detente
DOE Defame
DOE Defame
DOE Detente
DOE Defame
DOE Detente
EPASuperfund
EPASuparfund
DOE
DOE RiD
FUSRAP/SFMP
UMTRA
UMTRA
UMTRA
DOE Detente
DOE Detente
UMTRA
DOE Detente
DOE Detente
DOE Detente
UMTRA
UMTRA
Perfomance atteimnent
DOE Detente
DOE Detente
DOE Detente
CONTAMINANT
vccs
VOC't
Tritium and Radon
Tritium and Radon
Tritium and Radon
Tritium and Radon
PCB't
Non-reacrtvo tolute
TCAPu- 238,238
radlonucllda end nonradlologlc
Uranium teries liotopet
flow
variably tatu rated flow
variably tatu rated flow
recharge
flow
variable tatu rated flow
SCE.TCE.1.1-DCE
PCE.TCE,1,2-DCE,1,1-DCE. Bvlum
U.NO3. SO4
nat. enr U. Danturanlci. flit Ion
NA
Most radiobotopes
nat. enr U. banturanlcs. fltllon
VOC't
radlonuclldcs and nonradioloalc
ENDPONT
environmental concentration
groundwatar concentration
environmental concentrations
environmental concentration!
environmental concentrations
environmental concentrabont
environmental concentration
two— phase flow and concentration
environmental concentration
environmental concentraliont
dote commitment
hyd head datr and degree of tel
toll tentlon
rate of recharge to unconflned aguller
gw flux of meteoric w to w table
env cone and worat case dose
env cone and worst case dote
cone in ground water
dote
failure surfaces, factor! of safety
concetration and dose
dote
groundwaler concentration!
cone at water table, downttr wells
EFFORT
unknown
5mm
100 mm
6 mm
6mm
12 mm
2mm
u needed
38mm. Mmm
1-2FTE
6 mm
9 mm
as needed
amv/Yt
2 mm
amy/yr
25mm
2-3 FTE
V/C-
YES
NO
YES
YES
YES
NO
NO
NO
NO
NO
YES
YES
NO
YES
YES
NO
YES
NO
NO
YES
NO
YES
PUBLICATION
NO
NO
YES
NO
YESLANL Report LA-9967-MSn
NO
YES publ In an ES
YES
NO
YES ORNL draft report 1960
YES ORNL/M- 1045
YES
NO
YES
YES
NO
YES
NAME
Etztfxm lUctvr
avyOMlot
B«ryRoe«rn
F Tom Uudtrom
FTomlluaM-om
FTomUueerom
FTomUueftTem
ST^S2*'
TVnMcCjrsn
BnjuOallarw
PaJ Mmngjy
Or OwlayVu
Ma-Jn W Htrarton
TVnOovIng i
UnoaPaguel
McrMlJ Fayv
Or JvryO Oarfi
UndiP>gu»
KA Wdkr
KA WIMr
ThiOoenrxi
TE MVK*
MmnW Hancarton
RK.WNH
T£ Myo*
BarvRoBent
TtnLaOora
lodai VMdaton/Calibratton at reported by turveyretpondtnl
-------
TAbLE 4 - Model-Sponsoring Agency
16-Mar-93
Department
ARCL
BIOTRAN
CFEST
DECHEM
DITTY
DOSES
DOSTOMAN
EQ3/6
of Energy
FEMWATER/FEMWASTE
GENII
HARM-II
ISOSHLD
LTSAMP
MEPAS
ML CODE
RESRAD
MAT123D
PORFLO
PORMC-3
RHS-LC
RSAL
SUMD
TRACR3D
Environmental Protection Agency
AIRDOS (-EPA, -PC, MICRO-)
CAP-88
CHARM
COMPLY
CREAMS
DARTAB
HELP
HRS-I
HSPF
INPUFF
ISCST.LT
MINTEQ
PATHRAE (-EPA.-HAZ)
PRESTO
RADRISK
SCREEN
SIMS
UTM
Nuclear Regulatory Agency
CONDOS-II
DPCT
IMPACTS (PART61.-BRC)
MACCS
MAXI1
MESOI
MILDOS (-AREA)
NEFTRAN II
NUREG-0707
ONSITE
PAGAN
PATHRISK
RAECOM (RADON)
RASCAL
SWIFT (-11.-Ill)
TEMPEST/FLESCOT
TOUGH
Other
3d Mixing Cell
AFTOX
BALANCE
BARRIER
Bechtel
BRUNZOG
GENNMOD
GW FLOW
GEOFLOW
HEC-1,-2
MOC
MODFLOW (MOD3D)
ODAST
PATH
PC-SLOPE
PHREEQE
PLASM
RANDOM WALK
RETC.F77
STRIPD
SFRIPE
SOIL
STABL
STABL5
STABLR
STEPH
SURFER
UNSAT(-2,-H)
UTEXAS2
VAM2D
Unknown
CASCADER
CONSOL
CYLSEC
DCM3D
DECOM
FLASH/FLAME
FLOWPATH
FTWORK
GCDT3DH3.4.5
HYDROGEOCHEM
NEWBOX
ODRECH6.7
SEFTRAN
SOLUTE
SOURCE 2
SPUR
STRIP 1B
TDRECH11
THEM
,12,21,23
27
-------
TABLE 5: Index ol Existing Environmental Pathway Models
S
u
r
V
e
y
S
u
r
V
e
y
II
N
0
n
e
Agency
Multi-Media
Hazard Ranking
DPM
HRS-1
RHRS-LC
e
•
•
000
EPA
DOE
Radioactive Materials Fate & Transport
COMPLY (-11)
DECHEM
DECOM
DITTY
DOSES
DOSTOMAN
GENII
GENMOD
GRDFLX
IMPACTS (PART61) (-BRC)
MILDOS(-AREA)
NUREG-0707
ONSITE/MAXI1
PAGAN
PATH
PATHRAE (-EPA.-HAZ)
PRESTO-II
PRESTO-EPA (-DEEP.-BRC,-CPG,-POP)
RESRAD
UDAD
•
•
•
•
e
•
•
•
•
•
•
•
•
•
•
•
•
e
e
e
•
e
e
e
e
•
EPA
DOE
DOE
ORNL/DOE
DOE
Hanford/DOE
AECL
NRC
RSIC/NRC
NRC
NRC
PNUNRC
NRC
General Electric Corp.
EPA
DOE/EPA
ANUDOE
NRC
General Purpose
ARCL
Bechicl propneliiy
CASCADER
CONDOS(-I!)
ENPARTJcf.GEMS)
FLOWPATH
FTWORK
GCDT3DH (-3.-4.-S)
GEMS
MICROBE-SCREEN (cf GEMS)
MEPAS
MULTIMED
ODRECH(-6,-7)
PATHRISK
SPUR
STRIP IB
SUMO
TDRECH(-ll,-l2.-2l.-23)
TOX -SCREEN (cf GEMS)
UTM(-TOX)(cf GEMS)
•
•
•
•
•
e
•
e
e
•
•
e
•
•
•
•
•
•
•
e
•
•
DOE
Bechtel Corp
NRC
EPA
EPA
EPA
DOE
NRC
DOE
EPA
ORNL/EPA
Foodchain
BIOTRAN
INGDOS
TERRA
THEM
•
•
•
•
LASL/DOE
28
-------
TABLE 5: Index of Existing Environmental Pathway Models
Air
ADPIC
AFTOX
AIRDOS(-EPA. -PC, MICRO-, -AIRI)
ANEMOS(CRR!S)
AVACTRAII
AVLAGPAR
BOXMOD
CALINE-3
CAP-88
CHARM (EIS)
COMPLY
COMPLEX-1
CRAC2
DACRIN
DARTAB
GAMS
CASPAR
HARM -II
INPUFF(ef.GEMS)
ISC (-LT.-ST.BREEZE -AIR.-HAZ.-WAY)
KRONIC
LTSAMP
MESOI
ML CODE
PAVAN
PHAST
PTPLU-2
RAECOM
RSAC-3
RISKPRO-ACSI
SCREEN
SIMS
SUBDOSA
TECJET
TOXBOX
UNAMRP
XOQ/DOQ
S
u
r
V
e
y
•
•
•
•
•
e
•
•
•
•
S
u
r
V
e
y
u
•
•
•
N
o
n
e
•
•
•
•
•
•
Agency
U.S. Army
RSIC/ORNUEPA/Galson T. S Inc.
AeroEnvironment Inc
AeroEnvironment Inc.
California DOT
EPA
EPA/Radian Corp./Res Alt Inc.
EPA
EPA
DOE
EPA/Bowman Env
EPA/Bowman Env/Trinity Cons.
DOE
NRC
DOE
.
Technica Inc.
NRC
General Services Corp.
EPA
EPA
Technica Inc
Bowman Env /Env. Inc./Clary Ass.
NRC
29
-------
TABLE 5- Index of Existing Environmental Pathway Models
S
u
r
V
e
y
s
u
r
V
e
y
n
N
o
n
e
Agency
Surface Water
Runoff
Agricultural
GLEAMS (CREAMS)
HSPF
MRI
PRZM(PREPRZM)(cf GEMS)
STREAMS
WQAM
•
USDA
EPA
EPA
Urban/Suburban
HSPF
MRI
STORM
SWMM
WQAM
•
Landfill
HELP
MRI
SARAH
WQAM
•
•
•
•
e
•
EPA
EPA
•
•
•
EPA
Undeveloped
GLEAMS (CREAMS)
HSPF
MRI
WQAM
•
e
•
•
USDA
EPA
Streams
Flow
OYNHYOS(wcWASP4)
HEC(-l,-2)
HYDRO2D-V
QUALZE
SBUHYD
TEM PEST/FLESCOT
TR-20
•
•
•
•
•
•
•
Army Corps of Engineers
Univ Calif Santa Barbara
NRC
Transport
DYNTOX
EUTRO4(seeWASP4)
MEXAMS
MICHRIV
REACHSCAN
SARAH2
SLSA
TOXI4 (cf WASP4)
WQAM
EPA
30
-------
TABLE 5: Index of Existing Environmental Pathway Model*
S
u
r
V
a
y
i
s
u
r
V
•
y
ii
N
o
n
0
Agency
Flow and Transport
C EQUAL RIVl
CEQUALW2
CODELL
HSPF
QLPLOT
QUAL2E(AQUAL2)
RIVMOD
WASP4
e
NRC
EPA
EPA
Multiple Surface Water Flow and Transport
CORMIX
EXAMS (II) (cr GEMS)
•
a
EPA
Foodchain
BIODOSE
FGETS
LAOTAPII
PABLM (FOOD ARRRG)
a
a
a
a
31
-------
S: Index ol Existing Environmental Pathway Models
S
u
r
V
a
y
i
s
u
r
V
e
y
M
N
o
n
0
Agency
Groundwater
Groundwater Flow
Well Analysis
AQUIX
FASTER
GWAP
PARADOP
PTDPS(-I.-IIJII)
PUMP
PUMPING TEST PROGRAM PACKAGE
SLUGIX
STEP-MATCH
THEISFIT
TS-MATCH
TYPCURV
WELLFRAC
WHIP
Drawdown
ANALYTICAL MODELS
GLOVER
HYDROPAU1
THEIS
THEIS2
UT1L2
WATER-VEL
Unsaturated- 1d
HELP
VADOFT(ef RUSTIC)
•
•
EPA
EPA
Unsaturated-2d
MLTRAN
•
Unsaturated-3d
DCM3D
VADOSE
•
•
Saturated- id
ODAST
SOIL
e
e
American Geophys Union
IGWMC
Saturated-2d
AQUIFEM
BEWTA
COOLEY
FLUMP
FRESURF(-l.-2)
NUSEEP
USGS2D
V3
VTT
WELFLO
Nova Scotia Dept Env
R L Cooley, Nevada Univ.
S.P. Neuman, Umv Arizona
Northwestern Univ , Dept CE
uses
Illinois State Water Surv
PNL/DOE
32
-------
TABLE 5: Index of Existing Environmental Pathway Models
.
S
u
r
V
e
y
S
u
r
V
e
y
u
N
o
n
e
Agency
Saturated-ad
DPCT
EPA-WHPA
FE3DGW
OWFUD
MAT123D
RADIAL FINITE DIFFERENCE MODEL
RETCF77
TERZAGI
USGS3D (ModuUr.Tnscott)
WELLFLO
e
e
•
•
e
e
•
•
•
e
•
PNL/WISAP
USDA
T.N. Narasimhan, Umv California
USGS
Unsaturated/Saturated- id
UNSAT1D
•
U.S. Salinity Lab/DOE/NRC/PNL
Unsaturated/Saturated-2d
FEMWATER(cf FEMWASTE)
MAGNUM 2D
MMT
TRUST (-11)
UNSAT(-H.-2)
MOD2D(-FD)
PATHS
e
DOE
EQ&Q Idaho
U.S Salinity Lab./DOE/NRC/PNL
USGS
PNL/WISAP
Unsaturated/Saturated-3d
FREEZE
GEOFLOW
GWFLOW
MAGNUM 3D
MOD3D (-FD) (MODFLOW) (MODINV) (MACMODFLOW)
PATH3D
PCHST3D
PLASM
e
•
•
•
•
•
•
e
•
R.A. Freeze. Univ. Waterloo
NSEL.Canada
EG&G Idaho
USGS
Illinois State Water Survey
33
-------
TABLE 5: Index of Existing Environmental Pathway Models
S
u
r
V
e
y
i
S
u
r
V
e
y
u
N
0
n
e
Agency
Groundwater Flow and Transport
Unsaturated- id
CHEMFLO
GLEAMS
ICE-1
PRZM (cf RUSTIC)
RITZ
TETRANS
VADOFT
Unsaturated-2d
BIOPLUMEII
FLOWS
GS2
PORFLO-2D
TRIPM
WAFE
Hanford/OOE
Unsaturated-3d
CHAMP
GS3
PERCOL
PORFLO-3D
PORMC-3
TOUGH
•
•
•
e
•
•
ANL/PNL/ORNL
Hanford/OOE
Hanford/DOE
Saturated- 1d
AGU-IOPKG(ODAST)
GETOUT
GWMTMI.2
LAYFLO
MMT
NWFT/DVM
•
American Geophys. Union
PNUDOE
Princeton Univ.
PNL/DOE
Saturated-2d
ASM
CA1TI
CONMJG
DPCT
DUGUID-RCEVES
EPA-VHS
FTRANS
GWMTM2
GWTHERM
HYDROPAL
ISQUAD (-2)
KONBRED(cf MOC(USGS))
MAGNUM2D-CHAINT
OGRE
PATHS
PLUME (-2D)
PORFLO2D
PTC
RANDOM WALK
RESTOR
ROBERTSON(-l.-2)
SAFTMOD (cf RUSTIC)
SALTRP
SHALT
e
•
e
e
•
•
•
•
e
•
e
•
•
•
•
e
e
•
•
•
•
•
•
•
e
CGS. Inc
ORNL
EPA
Dames & Moore, Inc.
Princeton Univ./Univ Waterloo
USGS
LLNL
EPA
Illinois State Water Survey
uses
AECL
34
-------
TABLE 5: Index of Existing Environmental Pathway Models
TRAFRAP-WT
TRANS
s
u
f
V
e
y
i
s
u
r
V
e
y
u
Saturated-3d
AT123D(cf GEMS)
CFEST
GROVE/GALERKIN
GWTR3D
IIST3D
FINDER
PLUME
PRINCETON
SOLUTE PKG
SWENT
SWIP2
TRANSAT2
•
•
•
N
o
n
e
•
•
•
Agency
USGS
ORNL
PNL/DOE
USGS/Water Resorces
Princeton Univ.
INTERA Env Cons. Inc.
SNL/USGS/INTERA Env. Cons Inc.
GTC, Canada
Unsaturated/Saturated- 1d
CHAIN
CHAINT
CXPMPM
HYDRUS
ONE-D
PULSE
SI-SOIL (cf EMS)
SUMATRA-I
WORM
EG&G Idaho
Hanford
U.S. Salinity Lab.
Unsaturated/$aturated-2d
FEMWASTE(ef FEMWATER)
GROUNDWATER PACKAGE
LPMM
MOC(USGS)
MOD30
RW-ANALYT
SATURN
SUTRA
TDPLUME
TRANUSAT
TWODPLME
VAM2D
VS2DT
WOAM
•
•
•
•
•
•
•
•
•
•
•
•
•
•
•
•
DOE
USGS
USGS
GEOTRANS, Inc.
USGS/IGWMC/NWWA
GTS. Ltd
Hydrogeologic
USGS
35
-------
TABLE 5: Index of Existing Environmental Pathway Models
S
u
r
V
a
y
i
s
u
r
V
e
y
n
N
0
n
e
Agency
Unsaturated/Saturated-3d
3-d MIXING CELL
BEAVERSOFT
FLOWTHROUGH
KINZALBACH
MAT123D
MTJD(cfMODFLOW)
NEFTRANII
NUTRAN
NWFT/DVM
PORFLQ3D
RUSTIC
SEFTRAN
SEGOL
SLM
SWAN FLOW
SWIFT (-II.-III)
TARGET
TRACER3D
TR1PM
TRUST (MLTRAN) (-11)
WALTON PKG («)
•
•
•
•
•
•
•
•
•
•
•
•
•
•
•
•
•
•
•
•
•
•
DOE
S.S. Popadopulos & Associates
SNL/NRC
Hanford/DOE
SNL/NRC/GeoTrans. Inc
LANL/DOE
LBL/NRC
36
-------
TABLE 5: Index of Existing Environmental Pathway Modela
S
u
r
V
e
y
1
S
u
r
V
e
y
n
N
o
n
e
Hfleney
Aqueous Geochemistry
Geochemical
BALANCE
BCHEM
EQ3/6
EQUILB
GCSOLAR
HYDROGEOCHEM
MINTEQ (-A2) (PRODEFA)
PHREEQE
SOILCHEM
TRANSCHEM
WATEO4F
•
•
•
•
•
•
•
•
•
•
•
uses
DOE
EPA
uses
Hydrochemical
CHEMTRN
CHEMTRNS
CPT
CTMID
DYNAMIX
FASTCHEM (cf. ECHEM)
FIESTA
MININR
TRANQL
THCC
-
Engineering/Pertormance/Accident
ANISN
BARRIER
BRUNZOO
BLT(cf FEMWASTE)
CONSOL
DOT
FLASH/FLAME
HELP
MACCS
MORSE-SGS/S
NUTRAN
NEWBOX
ORIGEN-S
PC -SLOPE
RADTRAN(-Il)
RASCAL
RSAC
SFRIPD
SFRIPE
STABL5
STABL
STABR
STEPH
UTEXASZ
•
•
•
•
•
•
•
•
•
•
•
•
•
•
•
EPRI
U.S. Army
DOE/EPA
EPA
NRC
AECUUCRL
Geo-Slope, Canada
NRC
DOE/EXXON
MK Environmental, Inc
MK Environmental, Inc
DOT
R.A. Siegel, Purdue Univ
Univ. Calif. Berkeley
MK Environmental, Inc
Texas St. Dept. Hwy. & Pub. Trans.
37
-------
TABLE 5: Index of Existing Environmental Pathway Models
S
u
r
V
e
y
I
S
u
r
V
e
y
II
N
o
n
e
Agency
Radiation Dose
ANDROS
ANISN/PC
CRAC2
CYLSEC
DACRIN (cf. PABLM)
DOSHEM
HUMTRN
ISOSHLD
LADTAP
ORIGEN2
QAD-FN
RADRISK
REDIQ
SOURCE 2
e
e
•
e
•
•
e
e
e
•
•
•
•
•
RSIC/ANL
RSIC/BNWL/DOE
NRC
RSIC/ORNUDOE
RSIC/INEL
EPA
Utilities
ANNIE-IDE
GKS
SURFER
•
e
e
ANSI/Spectragraphics. Inc
Golden Software. Inc.
38
-------
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41
-------
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53
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Pacific Northwest Laboratory, Richland, Washington.
Trescott, P.C., Pinder, G.F., and, Larson, S.P., 1976. Finite-difference model for
aquifer simulation in two dimensions with results of numerical experiments.
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54
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Tsang, T.W., and Tsang, C.F., 1987. Channel model of flow through fractured media.
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55
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Appendix A - BACKGROUND INFORMATION ON IDENTIFIED MODELS
Model Descriptions and References
Model Classification Page
MULTI-MEDIA
HAZARD RANKING 62
HRS-1 62
MEPAS 62
RADIOACTIVE MATERIALS TRANSPORT & FATE 63
ARCL 63
DECHEM 63
DITTY 63
DOSES 63
DOSTOMAN 64
GENII 64
GENMOD 64
MILDOS 64
MILDOS-AREA 65
NUREG-0707 65
PATH 65
PATH1 65
RESRAD 66
IMPACTS (PART61) 67
ONSITE/MAXI1 68
PATHRAE (-EPA) 68
PRESTO-II 68
PRESTO-EPA 69
PRESTO-EPA-CPG 69
PRESTO-EPA-DEEP 69
PRESTO-EPA-POP 70
UDAD 70
GENERAL PURPOSE 71
CONDOS-II 71
FLASH/FLAME 71
SPUR 71
SUMO 71
UTM 71
FOODCHAIN 73
BIOTRAN 73
AIRTRANSPORT 74
AFTOX 74
AIRDOS (MICROAIRDOS, AIRDOS-PC) 74
CAP88(-PC) 74
CHARM 75
COMPLY ^..'75
DARTAB ...".......75
HARM-H ......16
INPUFF 76
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ISC(LT/ST) 76
LTSAMP 77
MESOI 77
MLCODE 77
PREPAR 77
RAECOM 78
SCREEN 78
SIMS 78
XOQ/DOQ 78
SURFACE WATER FLOW AND TRANSPORT 80
Codell Models 80
CREAMS 80
HEC-1 80
HEC-2 81
HSPF 81
SBUHYD 81
TEMPEST/FLESCOT 82
GROUND WATER
FLOW 83
FEMWATER 83
GWFLOW 83
MAGNUM (2D/3D) 83
MOD3D 84
MODFLOW 84
PLASM 85
RETC.F77 85
SOIL 85
TRUST 85
UNSAT2(-H) 86
TRANSPORT 87
CFEST 87
CHAINT 87
DPCT 87
FEMWASTE 88
MAT123D 88
MT3D 88
NEFTRAN(-H) 89
ODAST 90
PATHS 90
PORFLO (2D/3D) 91
PORMC-3 91
RANDOM WALK 92
SUTRA 92
SWIFT (II.IH) 92
TRACR3D 93
USGSMOC 93
VAM2D (H.3D.3DCG) 94
GEOCHEMICAL/HYDROCHEMICAL 95
BALANCE (-A) 95
EQ3/6 95
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HYDROGEOCHEM 95
MINTEQ(Al) 95
PHREEQE 96
ENGINEERING/PERFORMANCE/ACCIDENT 97
BARRIER 97
BRUNZOG 97
CONSOL 97
HELP 97
MACCS 98
ORIGEN2 98
PAGAN 98
PC-SLOPE 98
RASCAL 99
RSAC 99
SFRIPD 99
SFRIPE 99
STABL 99
STABL5 100
STABR 100
STEPH 100
UTEXAS2 100
RADIATION DOSE 101
ISOSHLD(-H) 101
LADTAP 101
RADRISK 101
UTILITIES 102
SURFER 102
NOTE: This appendix includes expanded listings for all of the models reported in the two Surveys and some
models not reported by respondents but known by the authors to be in use. Model descriptions included here
have been taken with minor editing from descriptions contained in the references. Any errors or omissions
in these descriptions are unintentional and are the responsibility of the authors of this report. We would
appreciate receiving notice of any such errors or omissions so that we can correct any future editions of the
text.
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MULTI-MEDIA - HAZARD RANKING
Model Name: HRS-1 (Hazard Ranking System-I)
Sponsor: USDOE
Description: Hazard ranking.
Reference: Stenner, R.D., R.A. Peloquin and K.A. Hawley. 1986. Modified Hazard Ranking
System/Hazard Ranking System for Sites With Mixed Radioactive and Hazardous Wastes - Software
Documentation. PNL-6066. Pacific Northwest Laboratory, Richland, Washington.
Model Name: MEPAS (Multimedia Environmental Pollutant Assessment System)
Sponsor: USDOE
Description: MEPAS is a risk computation system developed for hazard ranking applications. MEPAS is
designed to integrate the information available for defining chronic public health nsks associated with a
problem, or a series of problems. This system includes multi-pathway transport and fate models. Potential
problems may be characterized by either modeling the environment transport or by input of concentrations at
the receptor.
Individual and population environmental risks are evaluated from radioactive materials, chemical carcinogens,
and noncarcinogens by considering all major exposure pathways. An internal database provides chemical,
physical, and risk evaluation parameters for 297 constituents. Outputs include intermediate files (input
values, emission rates, environmental concentrations) and a file with impact information including maximum
individual and total population impact magnitudes, timing, and location.
Models are imbedded for air emissions (VOLATE), air transport processes (RAPSCD) and water transport
processes (RADCOND), and effects computation (HAZ). Gaseous and participate emissions/fluxes may be
estimated based on site conditions, or input as known parameters. The air transport is a sector average
Gaussian model with deposition and complex terrain modules that account for local terrain influences. The
soil transport can use dimensional advection and dispersion. In the vadose zone, the model has one
dimensional advection and dispersion. In the saturated zone, the model has one dimensional advection and
three dimensional dispersion. Various linkages of transport through soil, ground water, surface water and
overland runoff are supported.
MEPAS is implemented in MS-DOS for use on an IBM-PC or compatible with a computer shell designed for
application to a large number of problems. This Shell allows problem definition, data entry, reference
tracking, and model running. A set of data input worksheets are generated for each problem for purposes such
as external review or project records.
Reference: Doctor, P.G., T.M. Miley and C.E. Cowan. 1990. Multimedia Environmental Pollutant
Assessment System (MERAS') Sensitivity Analysis of Computer Codes. Prepared for the U.S. Department of
Energy. PNL-7296, UC-602, 630. Pacific Northwest Laboratory, Richland, Washington.
Droppo, J.G., Jr., G. Whelan. J.W. Buck, D.L. Strenge, B.L. Hoopes and M.B. Walter. 1989.
Supplemental Mathematical Formulations: The Multimedia Environmental Pollutant Assessment System
(MEPAS). PNL-7201. Pacific Northwest Laboratory, Richland, Washington.
Whelan. G., D.L. Strenge, J.G. Droppo Jr., and B.L. Steelman. 1987. The Remedial Action Priority
System (RAPS'): Mathematical Formulations. PNL-6200. Pacific Northwest Laboratory, Richland,
Washington.
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MULTI-MEDIA - RADIOACTIVE MATERIALS TRANSPORT AND FATE
Model Name: ARCL
Sponsor: USDOE
Description: Method to evaluate decommissioning alternatives by using a site-specific radiation
scenario/exposure pathway analysis to determine the acceptable levels of residual radioactive contaminants
that remain.
Reference: Napier, B.A., and G.F. Piepel. 1988. A Manual for Applying the Allowable Residual
Contamination Level Method For Decommissioning Facilities On The Hanford Site. Pacific Northwest
Laboratory, Richland, Washington. PNL-6348/UC602.
Model Name: DECHEM
Sponsor: USDOE
Description: Multiple pathway model developed for use in determining acceptable levels of chemicals in soil
after clean-up of Uranium Mill Tailings Remedial Action Project Sites (UMTRA). The model considers
exposure through ingestion of contaminated drinking water, ingestion of contaminated food and inhalation of
resuspended soil contaminants.
Reference: Model prepared by the Radiological Assessments Corporation, Neeses, South Carolina.
Complete citation not provided by respondents.
Model Name: DITTY (Dose Integrated Over Ten Thousand Years)
Sponsor: USDOE
Description: DITTY was developed to determine the collective dose from long term nuclear waste disposal
sites resulting from ground water pathways. DITTY estimates the time integral of collective dose over a
ten-thousand year period for time-variant radionuclide releases to surface waters, wells or the atmosphere.
Reference: Napier, B.A..R.A. Peloquin, and D.L. Strenge. 1986. DITTY- A Computer Program for
Calculating Population Dose Integrated Over Ten Thousand Years. PNL-4456. Pacific Northwest
Laboratories, Richland, Washington.
Model Name: DOSES
Sponsor: ORNL
Description: Being developed/used to simplify QC requirements. DOSES calculates dose to man from
measured environmental samples.
Reference: Developed by ORNL for use at ORNL. Complete citation not provided by respondents.
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Model Name: DOSTOMAN
Sponsor: USDOE
Description: Model is designed to provide estimates of long-term dose to man from buned waste. The model
consists of compartments which represent different portions of the environment, including vegetation,
herbivores, atmosphere, ground water, surface water and man.
Reference: Root, R.W. 1981. Documentation and User's Guide for DOSTOMAN - A Pathways Computer
Model of Radionuclide Movement. DPST-81-S49, E.I. DuPonl de Nemours & Co.
C.M. King, E.L. Wilhite, R.W. Root, Jr., D.I. Fauth, K.R. Routl, R.H. Emslie and R.R. Beckmeyer, R.A.
Fjeld, G. A. Hutto and J. A. Vandeven. 198S. The Savannah River Laboratory DOSTOMAN Code - A
Compartmental Pathways Model of Contaminant Transport. Proceedings of the DOE Low-Level Waste
Management Program Seventh Annual Participants Information Meeting. Las Vegas, Nevada, 1985.
CONF-8509121-13.
Model Name: GENII (Hanford Env. Dosimetry System Generation II)
Sponsor: USDOE
Description: Comprehensive set of environmental pathway and internal dosimetry models. Composed of
seven linked computer codes and their associate data libraries
Reference: Napier, B.A., R.A. Peloquin, D.L. Strenge and J.V. Ramsdell. 1988. Hanford Environmental
Dosimetry Upgrade Project. GENII - The Hanford Environmental Radiation Dosimetrv System. 3 Volumes.
PNL-6584. Pacific Northwest Laboratories, Richland, Washington.
Model Name: GENMOD
Sponsor: Atomic Energy of Canada
Description: Calculation of internal dose.
Reference: Prepared by Atomic Energy of Canada for use by the Canadian Nuclear Industry. Complete
citation not provided by respondents.
Model Name: MILDOS
Sponsor: USNRC
Description: MILDOS was designed to compute environmental radiation doses from uranium recovery
operations.
Reference: Strenge, D.L. and T.J. Bander. 1981. MILDOS - A Computer Program For Calculating
Environmental Radiation Doses From Uranium Recovery Operations. NUREG/CR-2011, PNL-3767. Pacific
Northwest Laboratory, Richland, Washington.
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Model Name: MILDOS-AREA
Sponsor: USDOE
Description: MILDOS-AREA is an improved version of MILDOS. The MILDOS-AREA code provides
improved capability for handling large area sources and updates the dosimetry calculations. Runs on an
IBM-PC computer.
Reference: Yuan, Y.C., J.H.C. Wang; and A. Zielen. 1989. MILDOS-AREA: An Enhanced Version of
MILDOS for Large Area Sources. ANL/ES-161. Argonne National Laboratory, Illinois.
Model Name: NUREG-0707
Sponsor: NRC
Description: Site-specific limits for allowable residual contamination.
Reference: Eckennan and Young. Complete citation not provided by respondents.
Model Name: PATH
Sponsor: GE
Description: Used to implement residual radioactive material guidelines during decommissioning.
Reference: Prepared by Dr. Jaikai Lee for use at the General Electric Shippmgport Station. Based on
guidelines in: A Manual for Implementing Residual Radioactive Material Guidelines. USDOE.
Model Name: PATH1
Sponsor: USNRC - SNL
Description:. PATH1 models the physical and biological processes that result in the transport of
radionuclides through the Earth's surface environment and eventual human exposure to these radionuclides.
PATH1 is divided into two submodels. The Environmental Transport Submodel represents the long-term
distribution and accumulation of radionuclides in the environment. The Transport-to-Man Submodel
simulates the movement of radionuclides from the environment to humans.
PATH1 uses a generalized approach to the simulation of radionuclide transport from the ground water
through the environment and food chain to humans. The code is not tied to any specific site characteristics.
The Environmental Transport Submodel of PATH1 requires that the study area be divided into a number of
compartments, and radionuclide movement between these compartments is represented by a system of linear
differential equations. The user must specify the transfer and decay coefficients for this system of
compartments. In the Transport-To-Man Submodel, radionuclide ingestion is calculated on the basis of
simple food chains and concentration ratios, while the amount of each radionuclide inhaled is determined
from the amount of radionuclide-contaming soil suspended in the air. These calculated ingestion and
inhalation rates are input to the Sandia Dose and Health Effects model, DOSHEM which is incorporated into
PATH1.
The code can be run with the ground water code NWFT/DVM using a Latin hypercube sampling routine.
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Reference: Helton. J.C., and Kaestner, P.C., 1981. Risk Methodology for Geologic Disposal of Radioactive
Waste: Model Description and User's Manual, the Pathways Model. NUREG/CR-1636. vol. 1, SAND 78-
1711 AN.
Campbell, J.E., Longsine, D.E., and Cranwell, R.M., 1981. Risk Methodology for Geologic Disposal of
Radioactive Waste: The NWFT/DVM Computer Code User's Manual. NUREG/CR-2081, Sandia National
Laboratory.
Model Name: RESRAD
Sponsor: USDOE
Description: RESRAD (Gilbert, 1988) is an implementation of the analytical methodology recommended by
the Department of Energy in its guidelines (DOE Order 5400.5, Gilbert et al., 1989) for allowable
concentrations of residual radioactive material in soil encompassed by the Formerly Utilized Sites Remedial
Action Program (FUSRAP) and Surplus Facilities Management Program (SFMP). RESRAD is a multi-media
model which incorporates within it a number of media-specific models all of which have been chosen for their
reliability but general conservatism. Guideline values denved by the models are based on the method of
concentration factors (NRC, 1977; ICRP, 1984; Till and Meyer, 1983; NCRP, 1984).
Pathway analysis for deriving soil concentration guidelines for a specified dose limit is done in four stages:
• Source analysis
• Environmental transport analysis
• Dose/response analysis
• Scenario Analysis
Source analysis is done using a nondispersive equilibrium model of the leaching process. This is an idealized
process in which the rate of leaching is constant until a radionuclide has been completely removed from the
contaminated zone. Ingrowth and decay of radioactive materials are treated as if they occurred entirely in the
contaminated zone. A contaminated zone is treated as a single homogeneous or inhomogeneous source of
changing thickness, depth, and radionuclide concentrations due to leaching, erosion, ingrowth, and decay.
Principal radionuclides are those with half-lives greater than 1 year.
Environmental transport pathways include air (dust, radon, and other gases) and water (surface and ground
water). Air transport is accomplished by use of a simple mixing model rather than a Gaussian plume model.
The surface water is assumed to be a pond or lake for which (1) the water inflow and outflow are in steady-
state equilibrium, and, (2) the annual inflow of radioactivity into the pond or lake equals the annual quantity
of radioactivity leached from the contaminated zone. Two models are used for calculating the water/soil
concentration ratio for the ground water pathway segment of RESRAD: a mass balance (MB) model and a
dispersionless flow (DF) model. The ground water pathway models implemented in the RESRAD code apply
only to situations for which the hydrological strata can reasonably be approximated by a sequence of uniform,
horizontal layers.
Dose equivalents in organs or tissues of the body are calculated with models that :(L) describe the entrance of
materials into the body (respiratory and gastrointestinal tract) and the deposition and subsequent retention of
the radionuclides in body organs (referred to as metabolic models); and, (2) estimate the energy deposition in
tissues of the body (ICRP, 1979).
Soil guidelines are based on a family-farm exposure scenario. RESRAD code was developed by Argonne
National Laboratory for AEC/NRC.
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Reference: T.L. Gilbert. M.J. Jusko, K.F. Eckerman. W.R. Hansen. W.E. Kennedy, Jr., B.A. Napier and
J.K. Soldat. 1988. A Manual for Implementing Residual Radioactive Material Guidelines. January 1988.
For the U.S Department of Energy.
T.L., Gilbert, C.Yu, Y.C. Yuan, A.J. Zielen, M.J. Jusko, and A. Wallo III, 1989. A Manual for
Implementing Residual Radioactive Material Guidelines. June 1989. For the U.S. Department of Energy.
Model Name: IMPACTS (PART61)
Sponsor: USNRC
Description: IMPACTS is used to determine disposal facility radiological impacts, including ground water
migration and overflow impacts, intrusion and exposed waste impacts and exposures from potential
operational accidents.
PART61 is a system of codes and data files that implements an expansion of the IMPACTS analysis
methodology used during the development of the 10 CFR 61 rule and includes:
CLASIFY: Classifies waste streams into four classes
IMPACTS: Determines radiological impacts
INVERSE: Activity or concentration limits
ECONOMY: Costs of disposal
INTRUDE: Impacts of an intruder
VOLUMES: Waste stream annual volumes
Modifications of the IMPACTS methodology included in PART61 are:
1. an update of the low-level radioactive waste source term
2. consideration of additional alternative disposal technologies
3. expansion of the methodology used to calculate disposal costs
4. consideration of an additional exposure pathway involving direct human contact with disposed waste due
to a hypothetical drilling scenario; and,
5. use of updated health physics analysis procedures (ICRP-30)
Based on input from CLASIFY, IMPACTS is used to determine most disposal facility radiological impacts
for a given combination of:
1. waste streams and processing options
2. disposal technology alternatives, and
3. disposal site environmental settings.
Reference: Oztunali, O.I., W.D. Pon, R. Eng and G.W. Roles. 1986. Update of Part 61 Impacts Analysis
Methodology. Codes and Example Problems. Volume 2. NUREG/CR-4370-Vol.2
Oztunali, O.I., and G.W. Roles. 1986. Update of Part 61 Impacts Analysis Methodology. Methodology
Report. Volume 1. NUREG/CR-4370-Vol. 1
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Model Name: ONSITE/MAXI1
Sponsor: NRC - PNL
Description: ONSITE/MAXI1 was developed for use by NRC in reviewing license applications Tor onsite
disposal of radioactive waste. Several exposure pathways can be simulated to conduct a dose pathway
analysis for human intrusion scenarios.
Exposure pathways that can be evaluated include direct external exposure to contaminated soil or building
surfaces, inhalation of resuspended material, and ingestion of drinking water or terrestrial or aquatic foods.
The user may optionally select ICRP-26 or ICRP-30 dose conversion factors.
Reference: Napier, B.A., R.A. Peloqum, W.E. Kennedy, Jr., and S.M. Neuder. 1984. Intruder Dose
Pathway Analysis for the Onsite Disposal of Radioactive Wastes: The ONS1TE-/MAXI1 Computer Program.
NUREG/CR-3620 (PNL-4054).
Kennedy, W.E., R.A. Peloquin, B.A. Napier and S.M. Neuder. 1986, 1987. Intruder Dose Pathway
Analysis for the Onsite Disposal of Radioactive Wastes: The ONS1TE/MAX11 Computer Program.
NUREG/CR-3620, Supplement 1, 1986, Supplement 2, 1987.
Model Name: PATHRAE (-EPA)
Sponsor: USEPA
Description: Estimates annual whole-body doses to a critical population group from the land disposal of
below regulatory concern (BRC) wastes. PATHRAE-EPA is expanded from the PRESTO-EPA-CPG and
PRESTO-EPA-BRC models.
PATHRAE-EPA can be used to calculate maximum annual effective dose equivalent to a critical population
group and to an offsite population at risk. Maximum annual doses are calculated to workers during disposal
operations, to offsite personnel after site closure, and to reclaimers and inadvertent intruders after site
closure. The offsite pathways include ground water transport to a nver and to a well, surface (wind or water)
erosion, disposal facility overflow, and atmospheric transport. The onsite pathways of concern arise
principally from worker doses during operations and from postclosure site reclamation or intruder activities
such as living and growing edible vegetation on site and drilling wells for irrigation or drinking water.
Reference: Rogers, V. and C. Hung. 1987. PATHRAE-EPA: A Low-Level Radioactive Waste
Environmental Transport and Risk Assessment Code. Methodology and Users' Manual. EPA 520/1-87-028
Model Name: PRESTO-II (Prediction of Radiation Effects from Shallow Trench Operations)
Sponsor: USDOE
Description: PRESTO-II is designed to serve as a non-site-specific screening model to evaluate possible
health effects from shallow land and waste disposal trenches for a 1000-year period following the end of
disposal operations. PRESTO-II has been applied to simulate radionuclide transport at several DOE
low-level waste sites and for the USNRC in support of a de minimis classification for waste.
Human exposure scenarios considered include normal releases (including leaching and operational spillage),
human intrusion, and limited site fanning or reclamation. Pathways and processes of transit from the trench
to an individual or population include ground water transport, overland flow, erosion, surface water dilution,
suspension, atmospheric transport, deposition, inhalation, external exposure, and ingestion of contaminated
beef, milk, crops, and water. Both population doses and individual doses, as well as doses to the intruder
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and farmer, may be calculated. Cumulative health effects in terms of cancer deaths are calculated for the
population over the 1000-year period using a life-table approach.
Reference: Fields. D.E., C.J. Emerson, R.O. Chester, C.A. Little and H. Hiromoto. 1986. PRESTO-II: A
Low-Level Waste Environmental Transport and Risk Assessment Code. Oak Ridge National Laboratory, Oak
Ridge, Tennessee. ORNL-5970.
Model Name: PRESTO-EPA
Sponsor: USEPA
Description: Simulates transport of low-level radioactive waste material from a shallow trench site and
assesses human risks associated with such transport. This model was modified and added to create the
PRESTO family of models: PRESTO-EPA-POP, PRESTO-EPA-CPG, PRESTO-EPA-DEEP,
PRESTO-EPA-BRC and PATHRAE-EPA.
Reference: PRESTO-EPA: A Low-Level Radioactive Waste Environmental Transport and Risk Assessment
Code - Methodology and User's Manual. 1983.
Model Name: PRESTO-EPA-CPG
Sponsor: USEPA
Description: Estimates maximum annual whole-body dose to a critical population group from land disposal
of low-level waste by shallow or deep methods. The maximum annual dose associated with the post-
operational phase of low-level waste disposal facilities is determined. All major non-intrusive "human
exposure pathways are considered. Time periods up to 10,000 years following the end of disposal may be
The conceptual logic and control modifications made in developing the PRESTO-EPA-CPG code include the
simultaneous modeling of leaching from multiple waste forms, the output of organic dose summaries for
specified intervals of time, the calculation of nuclide-specific dose conversion factors used in determining the
total dose for each year, the determination of the maximum annual dose and the year in which it occurs, and
the output of the corresponding dose summaries and detailed D ARTAB tables..
Reference: Rogers. V. and C. Hung. 1987. PRESTO-EPA-CPG: A Low-Level Radioactive Waste
Environmental Transport and Risk Assessment Code. Methodology and User's Manual. EPA 520/1-87-026.
Cheng Yeng Hung, 1989. User's Guide for the SYSCPG Program - A PC Version of the Presto-EPA-CPG
Operation System. EPA 520/1-89-017
Model Name: PRESTO-EPA-DEEP
Sponsor: USEPA
Description: Estimate cumulative population health effects to local and regional populations from land
disposal of low-level waste by deep methods. The PRESTO-EPA-DEEP code considers low-level waste
disposal by deep well injection, hydrofracture, and deep geologic disposal. The code can be used for
simulating the behavior of a facility for up to 10,000 years following the end of disposal operations.
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The deep disposal scenarios implemented in the PRESTO-EPA-DEEP code consider only the naturally
occurring pathways such as natural ground water and surface water flows and atmospheric transport.
Intrusion scenarios such as accidental drilling, geological faulting, and the failure of the access shaft sealing,
have a probabilistic nature and are not considered. However, a reinlerpretation of certain PRESTO-EPA-
DEEP variables will permit a consideration of such stochastic events.
Reference: Rogers, V., and Hung, C., 1987. PRESTO-EPA-DEEP A Low-Level Radioactive Waste
Environmental Transport and Risk Assessment Code - Methodology and User's Manual. EPA 520/1-87-025.
Model Name: PRESTO-EPA-POP
Sponsor:
Description: Estimates cumulative population health effects from land disposal of low level waste by shallow
methods. Health effects to the basin population are calculated for a time period of up to 10,000 years. The
code simulates the leaching of radionuclides from the waste matrix, hydrotogical, hydrogeological, and
biological transport, the resultant human exposures, and finally the assessment of the probable health effects
for the entire regional water basin population.
The PRESTO-EPA-POP code allows the user to select special human exposure scenarios such as an
inadvertent intruder residing or fanning the site, as well as routine migration of radionuclides from the trench
through the bydrologic and atmospheric environmental pathways to crops and drinking water.
Reference: Fields. D.E., C.A. Little, F. Parraga, V. Rogers and C. Hung. 1981. PRESTO-EPA-POP: A
Low-Level Radioactive Waste Environmental Transport and Risk Assessment Code. Volume 1. Methodology
Manual. EPA 52If 1-87-024-1.
Fields. D.E., C.A. Little, F. Parraga, V. Rogers and C. Hung. 1987. PRESTO-EPA-POP: A Low-Level
Radioactive Waste Environmental Transport and Risk Assessment Code. Volume 2. User's Manual. EPA
521/1-87-024-2.
Cheng Yeng Hung, 1992. User's Guide for the SYSPOP Program - A PC Version of the Presto-EPA-POP
Operation System. EPA 400R 92003.
Model Name: UDAD
Sponsor: USNRC
Description: UDAD provides estimates of potential radiation exposure to individuals and to the general
population in the vicinity of a uranium processing facility.
Reference: M.H. Moment, Y. Yuan and A.J. Zielen. 1979. Uranium Dispersion and Dosimetrv (UDAD')
Code. NUREG/CR-0553. Argonne National Laboratory, Illinois.
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MULTI-MEDIA - GENERAL PURPOSE
Model Name: CONDOS-II
Sponsor: USNRC
Description:
Reference: Complete citation not provided by respondents.
Model Name: FLASH/FLAME
Sponsor:
Description:
Reference: Complete citation not provided by respondents.
Model Name: SPUR
Sponsor:
Description:
Reference: Complete citation not provided by respondents.
Model Name: SUMO
Sponsor: USDOE
Description:
Reference: Complete citation not provided by respondents.
Model Name: UTM
Sponsor: ORNL
Description: UTM does complete ecological interactions modeling (ground water and surface water
transport, vegetation uptake, nutrient recycling) through compartments in a watershed system.
UTM's air, land, and aquatic sub-systems are designed to be run in sequence. The atmospheric component is
based upon a Gaussian plume model and calculates deposition rate of aerosols for any point within a
watershed. Concentrations of airborne aerosols at ground level are also calculated. The model includes
point, area, line, and windblown sources for air pollutants. Deposition occurs by dry fallout and also by
washout caused by rain falling through the plume. Air concentrations and depositions depend upon source
strength, atmospheric stability, and wind speed and direction patterns. The deposition values calculated by
the atmospheric model are used for input to the land component of UTM.
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The basic assumption underlying the land component of the UTM is that water is the major earner or material
through the terrestrial system. Thus, trace-material transport can be modeled by combining hydrologic
calculations with consideration of the chemistry of trace materials in aqueous media. The terrestrial
component is structured to receive atmospheric wet- and dryfall input to a watershed canopy and then to
simulate its movement until it is discharged in stream flow. The model simulates the amount of material
washed from the canopy to the land surface during rainfall and allows for the exchange and uptake or
adsorption of materials on surface soil. Surface runoff and scouring of soil particles are considered, together
with leaching of trace elements into the soil profile. An experimentally derived equilibrium distribution
coefficient is used to estimate the concentrations of contaminants in subsurface soil water. This estimated
concentration and the rate of soil water drainage are combined to estimate a subsurface input to the stream
channel.
The outputs from the terrestrial component of UTM enter the channel component, where flows are calculated
using the Chezy-Manning equation. This portion of the program simulates transport of dissolved and
particulate materials in stream flow. Suspended and bed-load transport are considered by the model. Mixing
ands exchange between aqueous and solid phases for the particular chemical species of concern are also
simulated. If point-source discharges of known strength are released in the stream, the channel component is
capable of simulating their introduction and subsequent transport.
Reference: Patterson, M.R., et. al. , 1974. A User's Manual for the FORTRAN IV Version of Wisconsin
Hydrologic Transport Model. ORNL-NSF-EATC-7, Oak Ridge National Laboratory, Oak Ridge, TN.
R.J. Luxmore and D.D. Huff. 1989. Analysis of Biogeochemical Cycling in Walker Branch Watershed.
pp. 164-196. Springer and Verlag, New York, New York.
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MULTI-MEDIA - FOODCHAIN
Model Name: BIOTRAN
Sponsor: LASL
Description: Model is used to predict the flow of transuranic elements (TRU) through specified plant and
animal environments using biomass as a vector.
Reference: Gallegos, A.F., B.J. Garcia, and C.M. Sutton. 1980. Documentation of TRU Biological
Transport Model (BIOTRANV LA-8213-MS. Los Alamos Scientific Laboratory.
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AIR TRANSPORT
Model Name: AFTOX
Sponsor: U.S. Army
Description: Atmospheric transport.
Reference: Complete citation not provided by respondents.
Model Name: AIRDOS (MICROAIRDOS, AIRDOS-PC)
Sponsor: USEPA - Radiological Assessments Corporation
Description: A modified Gaussian plume equation is used to estimate horizontal and vertical dispersion of
radionuclides released from one (MICROAIRDOS) to six (AIRDOS) stacks or area sources within a polar-
gridded assessment area. Radionuclide concentrations (up to 12 in MICROAIRDOS and 36 in AIRDOS) in
food are estimated by coupling the output of the atmospheric transport code to the USNRC Regulatory Guide
1.109 terrestrial food chain models. Dose conversion factors are input to the code, and doses to man for each
distance and direction specified are estimated for total body, red marrow, lungs, endosteal cells, stomach
wall, LLI wall, thyroid, liver, kidneys, testes, and ovaries throughout the following exposure modes:
1) immersion in air containing radionuclides
2) exposure to ground surfaces contaminated by deposited radionuclides
3) immersion in contaminated water
4) inhalation of radionuclides in air
5) ingestion of food in the area.
The code may be run to estimate highest annual individual dose in the area or annual population dose. Ground
concentrations of radionuclide and intake rates by man are tabulated for each environmental location.
Exposures are also calculated and tabulated for inhalation of 222Rn short-lived progeny.
Reference: Moore, R.E., C.K Baes III, L.M. McDowell-Boyer, A.P. Watson, P.O. Hoffman, J.C.
Pleasant and C.W. Miller. 1979. AIRDOS-EPA: A Computerized Methodology for Estimating
Environmental Concentrations and Dose to Man From Airborne Releases of Radionuclides. ORNL-5532,
EPA 520/1-79-009, U.S. EPA, Office of Radiation Programs, Washington, D.C..
Till, J.E., K.R. Meyer and R.E. Moore. 1987. MICROAIRDOS User's Manual and Documentation.
Radiological Assessments Corporation, Neeses, South Carolina.
Model Name: CAP88 (-PC) (Clean Air Act Assessment Package-1988)
Sponsor: USEPA -USDOE - RSIC
Description: The CAP-88 model is a set of computer programs, databases and associated utility program for
estimation of dose and nsk from radionuclide emissions to air. CAP-88 is composed of modified versions of
AIRDOS-EPA and DARTAB.
CAP88 allows users to perform full-featured dose and nsk assessments for the purpose of demonstrating
compliance with 40 CFR 61.93. CAP88 differs from the dose assessment software AIRDOS in that it
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estimates risk as well as dose, it offers a wider selection of radionuclide and meteorological data, it provides
the capability for collective population assessments, and it allows users greater freedom to alter values of
environmental variables.
CAP88 uses a modified Gaussian plume equation to estimate the average dispersion of radionuclides released
from up to six sources. The sources may be either elevated stacks, such as a smokestack, or uniform area
sources, such as a pile of uranium mill tailings. Plume rise can be calculated assuming either a momentum or
buoyancy-dnven plume. Assessments are done for a circular grid of distances and directions for a radius of
80 km around the facility.
The program computes radionuclide concentrations in air, rates of deposition on ground surfaces,
concentrations in food and intake rates to people from ingestion of food products produced in the assessment
area. Estimates of the radionuclide concentrations in produce, leafy vegetables, milk and meat consumed by
humans are made by coupling the output of the atmospheric transport models with the USNRC Guide 1.109
terrestrial food chain models.
Dose and risk are estimated by combining the inhalation and ingestion intake rates, air and ground surface
concentrations with the does and risk conversion factors in ICRP Publication 26.
Reference: Parks, B.S., 1991. User's Guide for CAP88-PC: Version 1.0. EPA 520/6-91/022, U. S.
Environmental Protection Agency, Washington D.C.
Model Name: CHARM (Complex Hazardous Air Release Model)
Sponsor: USEPA/Radian Corp.
Description: Atmospheric transport and risk estimates.
Reference: Radian Corp., CHARM. 8501 Mopac Blvd., P.O. Box 9948, Austin TX 78766.
Model Name: COMPLY
Sponsor: USEPA
Description: Model is used to demonstrate compliance with the National Emission Standards for Hazardous
Air Pollutants (NESHAPS) for Radionuclides in 40 CFR 61, Subpart I. It has various levels of complexity,
the simplest being a list of tables of concentration and possession limits in EPA89. The most complicated
level is an air dispersion calculation using a wind rose.
Reference: U.S. Environmental Protection Agency, 1989. User's Guide for the COMPLY Code. EPA
520/1-89-003, U.S. Environmental Protection Agency, Office of Radiation Programs, Washington, D.C.
Model Name: DARTAB
Sponsor: USEPA
Description: DARTAB combines radionuclide environmental exposure data with dosimetnc and health
effects data to generate tabulations of the predicted impact of radioactive airborne effluents. DARTAB is
independent of the environmental transport code used to generate the environmental exposure data and the
codes used to produce the dosimetnc and health effects data. DARTAB is often used with AIRDOS and
RADRISK.
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Reference: Begovich, C.L., K.F. Eckerman, E.G. Schlatter, S.Y. Ohrand R.O. Chester. 1981. DARTAB:
A Program to Combine Airborne Radionuclide Environmental Exposure Data with Dosimetnc and Health
Effects Data to Generate Tabulations of Predicted Health Impacts. ORNL-5692. Oak Ridge National
Laboratory, Oak Ridge, Tennessee.
Model Name: HARM-II (Hazardous Atmosphere Release Model)
Sponsor: USDOE
Description: HARM-II performs dispersion calculations for both chemical and radiological releases. Both
heavy and simple gases can be modeled.
Reference: NOAA Atmosphere and Diffusion Turbulence Laboratory. Complete citation not provided by
respondents.
Model Name: INPUFF
Sponsor: USEPA - Bowman Engineering
Description: INPUFF simulates dispersion from semi-instantaneous or continuous point sources over a
spatially and temporally variable wind field. The algorithm is based upon Gaussian puff assumptions
including a vertically uniform wind direction field and no chemical reactions. The code can estimate
concentrations at up to 100 from multiple point sources.
INPUFF uses three distinct dispersion algorithms. For short travel time dispersion, the user has the option of
using either the Pasquill-Gifford (P-G) scheme or the on-site scheme. The third dispersion algorithm was
designed for use in conjunction with the P-G or on-site scheme when there are long travel times involved.
Features of the code include:
Optional stack downwash
Optional buoyancy induced dispersion
Wind speed extrapolated to release height
Temporally variable source characteristics
Temporally and spatially variable wind field (user supplied)
Consideration of terrain effects through user-supplied wind Held
Consideration of moving source
Optional user-supplied subroutine for selecting dispersion coefficients
Optional user-supplied subroutine for estimating plume rise, and
Removal through gravitational settling and deposition.
Reference: Peterson, W.B. and L.G. Lavdas. 1988. INPUFF 2.0 - A Multiple Source Gaussian Puff
Dispersion Algorithm User's Guide. U. S. Environmental Protection Agency, 1986 and Supplement, 1988.
Model Name: ISC(LT/ST) (Industrial Source Complex Dispersion Model)
Sponsor: USEPA
Description: Combines and enhances dispersion model algorithms to consider pollutant sources other than
emissions from isolated stacks, such as fugitive emissions, aerodynamic wake effects, gravitational settling
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and dry deposition in assessing the air quality impact of emissions from a wide variety of industrial source
complex sources. Two major programs: the ISC Short Term (ISCST) and ISC Long Term (ISCLT).
1SCST uses hourly meteorological data to calculate concentrations for time periods up to 24 hours. ISCLT is
and advance Gaussian plume model for atmospheric dispersion of pollutants, using statistical wind summaries
to calculate quarterly or annual ground-level concentrations of emissions.
Reference: Bowers, J.F., J.B. Bjorklund, and C.S. Cheney. 1979. Industrial Source Complex (ISO
Dispersion Model User's Guide. EPA-45015-79-030. H.E. Cramer Co., Salt Lake City, Utah.
Model Name: LTSAMP
Sponsor: USDOE
Description: air transport?
Reference: Prepared by Jacobs Engineering for DOE UMTRA Project. Complete citation not provided by
respondents.
Model Name: MESOI
Sponsor: USNRC
Description: Atmospheric transport and dispersion model.
Reference: Ramsdell, J.V., G.F. Athey and C.S. Glantz. 1983. MESOI Version 2.0: An Interactive
Mesoscale Lagraneian Puff Dispersion Model With Deposition and Decay. NUREG/CR-3344 , PNL-4753.
Pacific Northwest Laboratory, Richland, Washington.
Model Name: MLCODE
Sponsor: USDOE
Description: Used to estimate dose and uncertainties in dose estimates resulting from air releases.
Reference: Prepared by B. Napier for use in the Hanford Dose Reconstruction Project. Complete citation not
provided by respondents.
Model Name: PREPAR
Sponsor: USEPA
Description: Pre-processor for AIRDOS-EPA
Reference: Oak Ridge National Laboratory, 19xx . PREPAR: A User-Friendly Preprocessor to Create
AIRDOS-EPA Input Data Sets. ORNL-5952, Oak Ridge National Laboratory, Oak Ridge, Tennessee.
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Model Name: RAECOM
Sponsor: USNRC
Description: Code is used to calculate cover thickness and surface fluxes of radon emissions from uranium
mill tailings.
Reference: Rogers, V.C., K.K. Nielsen and D.R. Kalkwarf. 1984. Radon Attenuation Handbook for
Uranium Mill Tailings Cover Design. NUREG/CR-3533
Model Name: SCREEN
Sponsor: USEPA
Description: SCREEN incorporates a number of simple screening procedure for estimating the maximum
ground-level concentration of radionuclides for sources in simple flat or elevated terrain. SCREEN:
• accepts user-specified distances,
• performs inversion break-up and shoreline fumigation estimates,
• includes building downwash effects in the wake region,
• performs calculations for the cavity region, and
• includes an optional complex terrain screening procedure based on the VALLEY Model 24-hour
screening technique
Reference: Brode, R.W., 1988. Screening Procedures for estimating the air quality impact of stationary
sources. EPA-450/4-88-010.
Model Name: SIMS
Sponsor: USEPA
Description:
Reference: Complete citation not provided by respondents.
Model Name: XOQ/DOQ
Sponsor: USNRC
Description: XOQ/DOQ is used in the meteorological evaluation of routine releases from commercial
nuclear power reactors. The model uses a steady-state Gaussian plume assumption to implement Section C of
Regulatory Guide 1.111.
XOQ/DOQ calculates average relative effluent releases and average relative deposition values at locations
specified by the user and at standard radial distances and segments for downwind sectors. The code also
calculates these values at the specified locations for intermittent releases. XOQ/DOQ provides the following
options:
• both elevated and ground-level sources can be modeled;
• the effluent plume of elevated releases can undergo plume rise due to buoyancy and/or momentum;
• ground-level releases can be affected by the additional dispersion due to local building or terrain induced
wakes;
• measured wind speeds can be extrapolated to other elevations;
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• topography can be varied;
• the plume may be depleted by dry deposition; and
• relative effluent concentrations and average relative deposition values can be amended to reflect the
effects of local air recirculation or stagnation.
This code can be used to estimate ground-level radionuclide concentrations and deposition amounts associated
with atmospheric releases from waste repository operations. XOQ/DOQ calculates only normalized
radionuclide concentrations and deposition rates; it does not model the subsequent transport of these
radionuclides through the environment and food chain to man.
Reference: Sagendorf, J.F., and Gall, J.T., 1977. XOO/DOO program for meteorological evaluation of
routine effluent releases at nuclear power stations. USNRC, Washington, D.C., NUREG/CR-0324.
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SURFACE WATER FLOW AND TRANSPORT
Model Name: Codell Models
Sponsor: USNRC
Description: The Codell series of models are a collection of simple programs used by the Hydrologic
Eugineering Section for computing the fate of routinely or accidentally released radionuclides in surface water
and ground water. The models are straightforward simulations of dispersion with constant coefficients in
simple geometries. Models included can be used for rivers, lakes and ground water. Programs STTUBE and
TUBE are useful for two-dimensional dispersion of a continuous source into a nver after steady-state has been
attained. Program RIVLAK also simulates dispersion in a river, but the source can be either steady or
unsteady. RIVLAK can be used to calculate two-dimensional dispersion in the near-shore regime of large
lakes. The surface water models in the Codell codes ignore uptake of radionuclide on sediments.
GROUND is used for calculating dispersion in a three-dimensional aquifer and is most useful for determining
the concentration at wells downgradient of a source released from a vertical plane. Program GRDFLX
provides the same function, but it considers the source to be horizontal.
Reference: Codell, R.B., Key, K.T., and Whelan, G., 1982. A Collection of Mathematical Models for
Dispersion in Surface Water and Ground Water. NUREG-0868, U.S. Nuclear Regulatory Commission,
Washington, D.C.
Model Name: CREAMS
Sponsor: USDA-Agncultural Research Service, Southeast Watershed Research Lab
Description: The CREAMS model can simulate pollutant movement on and from a field site, including such
constituents as fertilizers (N & P), pesticides, and sediment. The effects of alternative agricultural practices
on water and land resources can be assessed by simulation of the potential water, soil, nutrient, and pesticide
losses in runoff from agricultural fields. By integrating climatic, geomorphic, agronomic, and soil data with
structural, cultural, and management systems, the model computes relative yields of sediment, nutrients, and
pesticides at the edge of field-sized units. The model structure consists of three major components:
hydrology, erosion/sedimentation, and chemistry. The hydrology component estimates the volume and rate of
runoff, evapotranspiration, soil moisture content, and percolation. The erosion/sedimentation portion of the
model considers the processes of soil detachment, transport, and deposition. The chemistry portion of the
model considers nutrients and pesticides. The transport of soluble and sediment-attached chemicals is
evaluated. Interaction between plants and chemicals within the root zone is also considered. The model is
designed to require a bare minimum of calibration parameters and land use strategies. The spatial scale of the
model is intended to be the size of an agricultural field. When calibrated with observed data CREAMS can
be used to provide predictive information.
Reference: Knisel, W.G., ed., 1980. CREAMS: A Field-Scale Model for Chemicals. Runoff, and Erosion
from Agricultural Management Systems. U.S. Department of Agriculture, Science and Education
Administration, Conservation Research Report 26, 643 pp.
Model Name: HEC-1
Sponsor: U.S. Army Corps of Engineers
Description: Calculation of flood hydrographs.
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Reference: HEC-1 Flood Hvdrograph Package. User's Guide. 1981. U.S. Army Corps of Engineers, The
Hydrologic Engineenng Center.
Model Name: HEC-2
Sponsor: U.S. Army Corps of Engineers
Description: The HEC -2 model calculates water surface profiles for open channels with steady, gradually-
varied flow. The effects of obstructions such as bridges etc. can be considered.
Reference: HEC-2 Water Surface Profiles. User's Manual. 1982. U.S. Army Corps of Engineers, The
Hydrologic Engineering Center.
Model Name: HSPF
Sponsor: USEPA, Environmental Research Lab, Athens, GA
Description: HSPF is a continuous simulation model that simulates the time history of the quantity and
quality of runoff from multiple-use watersheds and simulates processes occurring in streams or fully-mixed
lakes receiving watershed runoff. Water quality algorithms include BOD/DO dynamics, carbon, nitrogen, and
phosphorous cycles, suspended and attached phytoplankton, and one species of zooplankton. Submodels also
include sediment transport, pesticide routing and degradation kinetics, and sediment-pesticide interaction.
HSPF is a series of coupled computer codes designed to simulate: 1) watershed hydrology; 2) land surface
runoff; and 3) the fate and transport of pollutants in receiving water bodies. The hydrologic portions of the
model include 1) a watershed hydrology model similar to the Stanford Watershed Model; 2) a'runoff model
using algorithms similar to the Non-Point Source (NPS) model; and 3) a stream routing component using a
kinematic wave approximation. The degradation/transformation process included in the model are:
hydrolysis, photolysis, oxidation, volatilization, and biodegradation. The kinetic reactions are formulated as
second-order processes. Secondary or "daughter" chemicals are also simulated; up to two daughter chemicals
can be analyzed in a single simulation. The one dimension formulation limits application of the model to river
systems where pollutants are uniformly mixed both laterally and vertically; the kinematic wave formulation of
flow in rivers is not applicable to rivers where the gradient is very small or where backwater effects are
present; data requirements for the model may be quite extensive depending on the particular application; and
the zero-dimensional representation of lakes assumes that pollutants are uniformly mixed throughout and that
the lake is not stratified.
Reference: Johanson, R.C., Imhoff, J.C., Kittle, Jr., J.L., and Donigian, Jr., A.S., 1984. Hvdrological
Simulation Program - FORTRAN (HSPF): User's Manual for Release 8.0. EPA-600/3-84-066, NTIS PB84
157155.
Model Name: SBUHYD
Sponsor: U.C. Santa Barbara
Description: Calculates hydrographs.
Reference: Stubenhaer, J.M. 1975. The Santa Barbara Urban Hydrograph Method. National Symposium on
Urban Hydrology and Sediment Control. University of Kentucky, July 1975.
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Model Name: TEMPEST/FLESCOT
Sponsor: USNRC
Description: FLESCOT simulates radionucltde transport in estuaries to obtain accurate radionuclide
distnbutions which are affected by time-variance, three-dimensional flow, temperature, salinity and
sediments. FLESCOT is a modification of the hydro thermal model TEMPEST.
Reference: Trent, D.S. and Y. Onishi. 1989. Proceedings of the ASCE Specialty Conference: Eshianne and
Coastal Circulation and Transport Modeling. Model - Data Comparison. November 15-17, 1989, Newport
Rhode Island.
Onishi, Y. and D.S. Trent. 1982. Mathematical Simulation of Sediment and Radionuclide Transport in
Estuaries: FLESCOT. Battelle Pacific Northwest Labs, Richland, Washington. Prepared for USNRC.
NUREG/CR-2423.
Onishi, Y. and D.S. Trent. 1985. Three-Dimensional Simulation of Flow, Salinity, Sediment and
Radionuclide Movements in the Hudson River Estuary. Proceedings of the Specialty Conference. Hydraulics
and Hydrology in the Small Computer Age. Hydrology Division/ASCE, Lake Buena Vista, Florida, August
12-17, 1985.
Onishi, Y., D.S. Trent and A.S. Koontz. 1985. Three-Dimensional Simulation of Flow and Sewage Effluent
Migration in the Strait of Juan de Fuca, Washington. Proceedings of the 1985 Specialty Conference on
Environmental Engineering. EE Division/ASCE. Northeastern University, Boston, Mass. July 1-5, 1985.
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GROUND WATER - FLOW
Model Name: FEMWATER
Sponsor: USDOE - AECL
Description: FEMWATER simulates ground water dynamics in saturated-unsaturated subsurface systems and
is a complimentary code to FEMWASTE which simulates waste transport.
FEMWATER is a revised finite-element model of water flow through porous media. Modifications from a
previous version include:
1. computing the flow field in a way consistent with the finite-element approach;
2. evaluating the moisture content increasing rate within the region by a new method consistent with
solving for moisture content and pressure fields; and
3. treating the terms to ensure that a unique relationship between any nonlinear variable and pressure is
preserved.
The expansion provides four alternative numerical schemes that are more appropriate for many situations.
Reference: Pickens, J.F. and Grisak, G.E., 1979. Finite Element Analysis of Liquid Flow. Heat Transport
and Solute Transport in a Ground Water Flow System: Governing Equations and Model Formulation. AECL-
TEC-REC-81, National Hydrology Research Institute Inland Waters Directorate, Environment Canada, for
Atomic Energy of Canada Limited, Whiteshell Nuclear Research Establishment.
Model Name: GW FLOW
Sponsor: Natural Sciences and Engineering Council of Canada.
Description: Saturated ground water flow. Stochastic, finite-element, two-dimensional, fully saturated
steady state ground water flow.
Reference: Complete citation not provided by respondents.
Model Name: MAGNUM (2D/3D)
Sponsor: USDOE - EG&G Idaho
Description: MAGNUM simulate coupled heat and ground water flow in a saturated, fractured-porous
media. The MAGNUM computer code is available in two versions - a two-dimensional version, MAGNUM-
2D; and a three-dimensional version, MAGNUM-3D.
MAGNUM-2D simulates transient or steady-state ground water flow and/or coupled heat transport in a two-
dimensional Cartesian or axisymmetric domain. MAGNUM-3D simulates heat conduction or ground water
flow but does not account for the fully coupled processes. Both versions of the code have been extensively
verified and benchmarked.
Both versions of MAGNUM use a dual permeability approach to represent the hydraulic behavior of a
fractured-porous media. The porous zones in the domain are modeled using standard two- and three-
dimensional isoparametric finite elements. Discrete fractures are modeled using line or plate elements which
are embedded along the sides of the continuum elements. MAGNUM provides flow field calculations for
input to transport and pathlme-travel time models.
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Bolh MAGNUM codes are interfaced with a number of pre- and postprocessors for input/output generation.
In addition, MAGNUM-2D is generally used in conjunction with the CHAINT mass transport model. In a
similar fashion, MAGNUM-3D is interfaced with the FECTRA mass transport code.
Reference: Baca, R.G., Amett, R.C., and Langford, D.W., 1984. 'Modeling fluid flow in fractured porous-
rock masses by finite element techniques, * International Journal for Numerical Methods in Fluids, v. 4, p.
337-348.
England, R.L., Kline, N.W., Ekblad, K.J., and Baca, R.G., MAGNUM-2D Computer Code: User's Guide.
RHO-CR-143 P, Rockwell Hanford Operations, Richland, Washington.
Estey, S.A. Arnett, R.C., and Aichele, D.B., 1985. User's Guide for MAGNUM-3D: A Three-Dimensional
Ground Water Flow Numerical Model. RHO-BW-ST-67 P, Rockwell Hanford Operations, Richland,
Washington.
Model Name: MOD3D
Sponsor: USGS
Description: MOD3D simulates three-dimensional ground water flow in a porous, heterogeneous and
amsotropic medium with irregular boundaries.
Reference: McDonald, G., and Harbraugh, A.W., 1989. A Modular Three-Dimensional Finite Difference
Ground Water Flow Model: MOD3D. U.S.G.S. Techniques of Water Resource Investigations, Book, 6,
Chapter Al, TWI 6-A1, Washington, D.C.
Model Name: MODFLOW
Sponsor: USGS/IGWNC
Description: MODFLOW is a finite-difference model that simulates flow in three dimensions. Ground Water
flow within the aquifer is simulated using a block-centered finite-difference approach. Layers can be
simulated as confined, uncontined, or a combination of the two. Flow associated with external stresses, such
as wells, can also be simulated. The finite-difference equations can be solved using either the Strongly
Implicit Procedure (SIP) or Slice-Successive-Overrelaxation (SSOR).
Reference: McDonald, M.G. and A.W. Harbaugh. 1984. A Modular Three-Dimensional Finite Difference
Ground Water Flow Model: MODFLOW. U.S. Geological Survey Open File Report. 83-875.
Harbaugh, A.W., 1990. A Computer program for Calculating Subregional Water Budgets Using Results from
the U.S. Geological Survey Modular Three-Dimensional Finite-Difference Ground Water Flow Model:
MODFLOW. USGS Open-File Report 90-392, 46 pp.
Harbaugh, A.W., 1990. A Simple Contouring Program for Gndded Data. USGS Open-File Report 90-144,
37pp.
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Model Name: PLASM
Sponsor: Illinois State Water Survey
Description: Saturated, two dimensional ground water flow. Available for mainframe or PC computers.
Reference: Prickett, T.A. and C.G. Lonnquist. 1971. Selected Digital Computer Techniques for Ground
Water Resource Evaluation. Illinois State Water Survey, Urbana, Illinois.
Model Name: RETC.F77
Sponsor: USDA
Description: Estimation of hydraulic conductivity of unsaturated and porous media.
Reference: Mualem, Y. 1976. A New Model for Predicting the Hydraulic Conductivity of Unsaturated and
Porous Media. Water Resources Research. Vol 12, No.3
Model Name: SOIL
Sponsor: IGWMC
Description: Variably Saturated Flow.
Reference: El-Kadi, 198S. SOIL, version IBM-PC 1.0, International Ground Water Modeling Center, Butler
University, Indianapolis, Indiana.
Model Name: TRUST
Sponsor: USNRC - PNL
Description: TRUST provides a versatile tool to solve a wide spectrum of fluid flow problems arising in
variably-saturated, deformable, porous media. The governing equations express the conservation of fluid
mass in an elemental volume that has a constant volume of solid. Deformation of the skeleton may be
nonelastic.
Permeability and compressibility coefficients may be nonlinearly related to effective stress. Relationships
between permeability and saturation with pore water pressure in the unsaturated zone may include hysteresis.
The code developed by T.N. Narasimhan grew out of the original TRUMP code written by A.L. Edwards.
The code uses an integrated finite difference algorithm for numerically solving the governing equation.
Marching in time is performed by a mixed explicit-implicit numerical procedure in which the time step is
internally controlled. The time step control and related feature in the TRUST code provide an effective
control of the potential numerical instabilities that can arise in the course of solving this difficult class of
nonlinear boundary value problems.
Reference: Reisenauer, A.E., Key, K.T., Narashimhan, T.N., and Nelson, R.W., 1982. TRUST: A
Computer Program for Variably Saturated Flow in Multidimensional. Deformable Media. NUREG/CR-2360,
PNL-397S, U.S. Nuclear Regulatory Commission, Washington, D.C..
Edwards, A.L., 1968. TRUMP: A Computer Program for Transient and Steady State Temperature
Distributions in Multidimensional Systems. Rep. UCRL-14754, NTIS, Springfield, VA (Third Revision,
1972)
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Model Name: UNSAT2 (-H)
Sponsor: USDOE
Description: The UNSAT-H model simulates the water and heat balance of soils to predict ground water
recharge rates and to assess the ability of earthen covers to prevent drainage into underlying waste zones.
Version 2.0 of the UNSAT-H model simulates the process of water infiltration, redistribution, evaporation,
soil-water extraction by plants, deep drainage that becomes recharge, surface energy balance, and soil heat
flow. The mathematical bases are Richards equation for liquid flow, Pick's law for diffusion of water vapor,
Fourier's law for heat conduction, and the theory of coupled water and heat flow in soils proposed by Philip
and de Vries. The model is implemented in FORTRAN as a 1-dimensional finite-difference code with
variable time stepping and mass balance control. Verification and validation testing has been performed.
Future versions of the model are expected to address hysteresis, snow melt, freezing soil, the temperature
dependence of soil properties, a separate air phase, and multiple dimensions.
Reference: L.A. Davis and S.P. Neuman, 1983. Documentation and User's Guide UNSAT-2.
NUREG/CR-3390.
Payer, M.J., G.W. Gee and T.L. Jones. 1986. UNSAT-H Version 1.0: Unsaturated Flow Code:
Documentation and Applications for the Hanford Site. PNL-5899, Pacific Northwest Laboratory, Richland,
Washington.
Payer, M.J., and T.L., Jones, 1990. UNSAT-H Version 2.0: Unsaturated Soil Water and Heat Flow Model.
PNL-6779, Pacific Northwest Laboratory, Richland, Washington.
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GROUND WATER - TRANSPORT
Model Name: CFEST
Sponsor: USDOE
Description: Energy and Solute Transport.
Reference: Gupta, S.K., C.R. Cole, C.T. Kincaid and A.M. Monti. 1987. Coupled Fluid. Energy and
Solute Transport (CFEST) Model: Formulation and User's Manual BMI-ONWI-660. Office of Nuclear
Waste Isolation, Battelle Memorial Institute, Columbus Ohio.
Model Name: CHAINT
Sponsor: USDOE - Hanford
Description: CHAINT simulates multicomponent mass transport in a saturated, fractured-porous media.
The CHAINT computer code can simulate transient or steady-state mass transport including chain decay. The
two-dimensional code has been extensively verified and benchmarked.
The CHAINT code utilizes a dual permeability approach to represent a fractured-porous medium. The code
can handle heterogeneous, anisotropic systems with networks of discrete fractures. The porous zones in the
domain are modeled using standard two-dimensional isoparametric finite elements, i.e., triangles and
quadrilaterals. Discrete fractures are modeled using line elements which are embedded along the sides of the
continuum elements. In addition, the code can accommodate a variety of initial and boundary conditions.
The primary outputs of the CHAINT code are contaminant concentrations and fluxes at specified locations.
CHAINT is interfaced with MAGNUM-2D and with several pre- and post-processes.
Reference: Baca, R.G., Arnett, R.C., and Langford, D.W., 1984. 'Modeling fluid flow in fractured
porous-rock masses by finite element techniques," International Journal for Numerical Methods in Fluids, v.
4, p. 337-348.
Kline, N.W., England, R.L., and Baca, R.G., 1986. CHAINT Computer Code: User's Guide1 RHO-CR-144
P, Rockwell Hanford Operations, RichJand, Washington.
Model Name: DPCT
Sponsor: NRC
Description: DPCT (Deterministic-Probabilistic Contaminant Transport) predicts ground water flow and
contaminant transport accounting for advection, dispersion, radioactive decay, and equilibrium sorption for a
single contaminant.
The code treats a two-dimensional vertical cross-section. Almost any water table and geologic configuration is
permissible, and there are a variety of allowable boundary conditions. Water flow is steady state.
The cross section is divided into a rectangular array of cells. The head distribution is found by the finite-
element method. Solute transport is then treated by tracking the motion of individual particles.
The principal assumptions of the code are:
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1. a treatment in two-dimensional cross-section is acceptable;
2. the solute transport equation is valid;
3. sorption may be represented as equilibrium adsorption with a specified distribution coefficient;
4. principal axes of the transnussivity tensor are parallel to coordinate axes everywhere; and
5. ground water flows are steady state.
References: Schwartz, F.W., Crowe, A., 1980. A Deterministic-Probabilistic Model for Contaminant
Transport: DPCT. U.S. Nuclear Regulatory Commission Report NUREG/CR-1609.
Model Name: FEMWASTE
Sponsor: USDOE - AECL
Description: FEMWASTE simulates waste transport through porous media under dynamic ground water
conditions.
FEMWASTE is a finite-element model of waste transport through porous media which simulates the spatial
and temporal distributions of both waste concentration and flux under dynamic ground water conditions. The
transport mechanisms include advection, hydrodynamic dispersion, chemical sorption, and first-order decay.
Reference: Pickens, J.F. and Grisak, G.E., 1979. Finite Element Analysis of Liquid Flow. Heat Transport
and Solute Transport in a Ground Water Flow System: Governing Equations and Model Formulation. AECL-
TEC-REC-81, National Hydrology Research Institute Inland Waters Directorate, Environment Canada, for
Atomic Energy of Canada Limited, Whiteshell Nuclear Research Establishment.
Model Name: MAT123D
Sponsor: USDOE
Description: The computer model MAT123D was developed to simulate waste disposal systems. It can be
used to analyze the environmental impacts resulting from disposal of radioactive and chemical wastes in
geologic media. The process of infiltration through disposal cell caps, transient source leaching and solute
transport in geologic media are included. Situations involving saturated-unsaturated media under either
fractured or homogeneous conditions can be modeled.
Reference: Yu, C., 1987. A Simulation Model for Analyzing the Environmental Impact of Waste Disposal
Systems. Argonne National Laboratory, Illinois.
Model Name: MT3D
Sponsor: Papadopolus Inc.
Description: MT3D is a modular three-dimensional transport model capable of simulating advection,
dispersion, and chemical reactions of dissolved constituents in ground water flow systems (Geeing 1990).
MT3D was developed with support from the U.S. EPA and is distributed by the Kerr Laboratory.
MT3D was developed using a similar modular structure as MODFLOW, the U.S. Geological Survey modular
three-dimensional finite-difference ground water flow model (McDonald and Harbaugh 1988). The modular
structure facilitates linking of the program with a ground water flow model such as MODFLOW, simulating
transport processes independently thereby conserving computer memory for unused options, and also
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simplifies code modifications. It can be used in conjunction with any block-centered finite-difference flow
model, but is especially well-suited for linking with MODFLOW. The ground water flow model is
constructed and calibrated independently assuming that changes in the concentration field will not affect the
flow field measurably. MT3D uses the same spatial discretization and layer types ad MODFLOW. In
addition, the following transport boundary conditions are supported: 1) specified concentration or mass flux
boundaries; and 2) the solute transport effects of external sources and sinks such as wells, drains, nvers, area!
recharge and evapotranspiration.
MT3D includes four methods for solving the three-dimensional advective-dispersive-reactive equation:
Method of Characteristics (MOC), Modified Method of Characteristics (MMOC), Hybrid Method of
Characteristics, and the explicit finite-difference technique. The first three techniques solve the advection
term using a method-of characteristics scheme and the other terms using the finite-difference technique. The
MOC technique uses a conventional particle tracking technique for solving the advection term. MOC
virtually eliminates numerical dispersion, but can be slow and computationally intensive. This technique is
well-suited for problems where sharp concentration fronts exist. The MMOC technique is similar to MOC in
that it uses particle tracking techniques, but it involves fewer computations. The MMOC technique is best
suited for problems where sharp concentration fronts are not present and the error caused by numerical
dispersion can be considered insignificant. The HMOC technique is a mixture of MOC and MMOC, and
attempt to combine the strength of both through an automatic adaptive procedure. The HMOC technique is
well-suited for problems where sharp concentration fronts are present and can be more efficient
computationally than the standard MOC technique. The finite-difference technique uses Taylor-series to
approximate the derivatives, and is susceptible to numerical dispersion. The finite-difference technique is
normally more efficient computationally than the three method-of-charactenstics schemes and is best-suited
for problems where sharp concentration fronts are not present.
When modeling dispersion, MT3D can accept a different value for longitudinal dispersivity at each node.
One value per layer is then accepted for the horizontal and vertical transverse dispersivity ratios. Chemical
reaction currently supported by the MT3D model include equilibrium-controlled sorption reactions and first-
order irreversible rate reactions, such as radioactive decay or biodegradation. A single value per layer is
specified for bulk density of the porous medium and distribution coefficient. Porosity can be specified
individually for each node in the model. These parameters are used by MT3D to compute a retardation
factor.
Reference: Zheng, C., 1990. A Modular Three-Dimensional Transport Model for Simulation of Advection.
Dispersion and Chemical Reactions of Contaminants in Ground Water Systems. U.S. Environmental
Protection Agency, Robert S. Kerr Environmental Research Laboratory, Ada, OK.
Model Name: NEFTRAN(-II)
Sponsor: USNRC - SNL
Description: NEFTRAN simulates ground water flow and radionuclide transport in the saturated zone, and in
the unsaturated zone if moisture content and flow are constant. The code assumes that all flow is along one-
dimensional paths which are then assembled into multidimensional networks. Flow is determined by the
application of Darcy's law and by requiring conservation of mass at segment junctions. Dispersion is
accounted for by the distributed velocity method described by Campbell et al. (1981). The code accounts for
multiple straight and branched decay chains. The code has the capability to model the source term either as a
leach-limited or a solubility-limited source. In addition, the source term is decoupled from the flow and
transport sections so that each can be run independently. NEFTRAN is an improved version of the
NWFT/DVM (Campbell et al., 1981) code and has been shown to reproduce NWFT/DVM results.
Reference: Longsine, D.E., Bonano, E.J., and Harlan, C.P., 1987. User's Manual for the NEFTRAN
Computer Code. NUREG/CR^766, SAND86-2405.
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Olague, N.E., Longsme, D.E., Campbell, J.E., and Leigh, C.D., 1991 User's Manual for the NEFTRAN II
Computer Code. NUREG/CR-5618, SAND90-2089, Sandia National Laboratones, Albuquerque, N.M.
Model Name: ODAST
Sponsor: IGWMC - AGU
Description: ODAST is one program within the AGU-10 package of ground water flow and transport
models which includes the following subprograms:
LTIRD simulates dispersion in a radial flow field, calculating the dimensionless concentration of a particular
solute, injected into an aquifer, as a function of time and radius. It assumes fully penetrating injection wells
with constant injection rate and concentration at source in a homogeneous and isotropic aquifer of uniform
thickness. Background concentration of the contaminant is assumed to be zero. The evaluation of the
analytical solution is based on numerical inversion of Laplace transform equations.
ODAST evaluates one-dimensional analytical solute transport including convection, dispersion, decay (at the
source and in the aquifer) and adsorption. It can calculate relative concentration at any point downstream
from the contaminant source at any specified time. It assumes a homogeneous isotropic aquifer of uniform
thickness, steady-state flow field, and zero background concentration.
TDAST evaluates two-dimensional analytical solute transport. Convection, dispersion, decay (at source and
in the aquifer), and adsorption. Relative concentration can be calculated at any point downstream from a
finite strip source (orthogonal to the direction of flow) at any specified time. The model assumes a
homogeneous, isotropic aquifer of uniform thickness, steady-state flow field, and zero background
concentration.
RESSQ is a semi-analytical model of two-dimensional solute transport that calculates the streamline pattern in
an aquifer, location of contaminant fronts about sources at specified times, and concentration versus time at
sinks. The model assumes a homogeneous, isotropic, confined aquifer of uniform thickness, steady-state
flow field, and advection and adsorption only (no dispersion or decay). Sources are represented by fully
penetrating recharge wells and ponds, and sinks are represented by pumping wells.
RT converts a time series of concentration data from one or more observation wells into a spatial
concentration distribution in the aquifer at specified times. The model assumes a single fully penetrating
production well, steady-state radial flow field, and negligible regional flow.
Reference: Javendal, I., Doughty, C., andTsang, C.F., 1984. Ground Water Transport: Handbook of
Mathematical Models. American Geophysical Union, Water Resources Monograph 10, Washington, D.C.
Model Name: PATHS
Sponsor: PNL/DOE
Description: PATHS provides an approximate contaminant transport evaluation by direct solution of the
path!me equations. The steady cases are evaluated by holding the uniform gradient, the head in the pond, and
the well strengths constant. Under such steady-state conditions, only one set of flow paths, advancing fronts,
and travel times must be calculated. In the transient cases, each new set of fluid particles leaving the pond or
wells encounters changing velocity effects. Therefore, a range of typical departure times is selected and the
flow paths, front configurations, and travel limes are calculated successively for each selected set of fluid
particles leaving the contaminant source. The approximate equilibrium coefficient approach is used to give the
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ion exchange delay effects for a single constituent. There are, however, no dispersion effects considered in
the preliminary model. The model can consider as many as 35 wells at optional locations. Wells are
represented as numerically solved by the code to give the paths of the fluid particles and their advance within
time toward the outflow boundary.
The main assumptions of the code are1
1) two-dimensional (horizontal plane) infinite aquifer of constant thickness;
2) confined flow;
3) homogeneous, isotropic material with constant properties;
4) uniform flow direction may include transient gradient (flow) strength;
5) round, fully-penetrating wells and caverns;
6) dissipation of the well and cavern heads occurs over a specific radial distance;
7) diffusion and dispersion processes are neglected; and
8) contaminant adsorption is based on linear equilibrium isotherms.
Reference: Nelson R.W. and Schur, J.S., 1980. PATHS - Ground Water Hydraulic Assessment of
Effectiveness of Geologic Isolation Systems. PNL-3162, Pacific Northwest Laboratory, Richland, WA.
Model Name: PORFLO (2D/3D)
Sponsor: Hanford - PNL
Description: PORFLO simulates coupled heat, ground water flow and solute transport in a saturated or
unsaturated, porous media. The code is available in either two-dimensional, saturated flow (2D) or three-
dimensional (3D), unsaturated flow versions.
Both versions of PORFLO utilize the equivalent porous continuum analogy to represent a porous medium.
The codes can handle heterogeneous, anisotropic systems and can accommodate a variety of boundary
conditions. In addition, the codes use a free-format input mode which makes it exceptionally easy to setup an
input file. The codes also have various options that allow the user to select the processes to be modeled and
the solution method to be used. The codes provide flow field calculations for input to pathline-travel time
models and can be interfaced with a number of post-processors for graphical output.
References: Runchal, A.K., Sagar, B., R.B. Baca, and N.W. Kline, 1985. PORFLO - A Continuum Model
for Fluid Flow. Heat Transfer and Mass Transport in Porous Media: Model Theory . Numerical Methods.
and Computational Tests.. Rep. RHO-CR. 150 P, Basalt Waste Isolation Project, Rockwell Hanford
Operations, Richland, WA.
Runchal, A.K., and Sagar, B., 1989. PORFLO-3: A Mathematical Model for Fluid Flow. Heat and Mass
Transport in Variably Saturated Geologic Media - User's Manual - Version 1.0. Westmghouse Hanford
Operations, Richland, Washington.
Sagar, B., and Runchal, A.K., , 1990. PORFLO-3: A Mathematical Model for Fluid Flow. Heat and Mass
Transport in Vanablv Saturated Geologic Media - Theory and Numerical Methods. WHC-EP-0042,
Westinghouse Hanford Operations, Richland, Washington.
Model Name: PORMC-3
Sponsor: Hanford
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Description: Heat and solute transport.
Reference: Prepared by Analytic & Computational Research Inc. Complete citation not provided by
respondents.
Model Name: RANDOM WALK
Sponsor: Illinois State Water Survey
Description: Solute transport, two-dimensional porous media.
Reference: Prickett, T.A., T.G. Naymik, and C.G. Lonnquist, 1981. A Random Walk Solute Transport
Model For Selected Ground Water Quality Evaluations. Bulletin 65, Illinois State Water Survey,
Champaign, Illinois.
Model Name: SUTRA
Sponsor: USGS - International Ground Water Modeling Center - National Water Well Association
Description: SUTRA (Saturated-Unsaturated Transport) simulates fluid movement and the transport of either
energy or dissolved substances in a subsurface environment. The model employs a two-dimensional hybnd
finite-element and integrated finite-difference method to approximate the governing equations that describe
the two interdependent processes that are simulated:
1. fluid density-dependent, saturated or unsaturated, ground water flow; and
2. a. transport of a solute in the ground water, in which the solute may be subject to equilibrium adsorption
on the porous matrix, and both first-order and zero-order production or decay, or
2. b. transport of thermal energy in the ground water and solid matrix of the aquifer.
Reference Voss, C.I., 1984. SUTRA - Saturated-unsaturated Transport: A Finite-Element Simulation
Model for Saturated-Unsaturated. Fluid density-Dependent Ground Water Flow with Energy Transport or
Chemically-Reactive Single-Species Solute Transport. U.S. Geological Survey, Reston, Virginia. .
Model Name: SWIFT (11,111)
Sponsor: USNRC
Description: SWIFT II & III simulate the flow and transport of energy, solute and radionuclides in a
geologic medium.
Reference: Reeves, M., D.S. Ward, N.J. Johns and R.M. Cranwell. 1986. The Sandia Waste-Isolation
Flow and Transport Model For Fractured Media: Release 4.84: Theory and Implementation. USNRC,
Washington, D.C. NUREG/CR-3328.
Reeves, M. and R.M. Cranwell. 1981. User's Manual for the Sandia Waste-Isolation Flow Transport Model
(SWIFT). USNRC, Washington, D.C. NUREG/CR-2324.
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Model Name: TRACR3D
Sponsor: USDOE - LANL
Description: TRACR3D simulates fluid flow and mass transport in a saturated or unsaturated, porous
medium. The code is primarily applied to field problems involving unsaturated conditions.
TRACR3D utilizes the equivalent porous continuum analogy to represent a porous media. The code can
handle heterogeneous, anisotropic systems and can accommodate a variety of boundary conditions. The code
is relatively easy to use but can be run on a Cray computer only. The code has various options that allow the
user to select the processes to be modeled and the solution method to be used.
Reference: Travis, B.J., 1984. TRACR3D: A Model of Flow and Transport in Porous Media. LA-9667-
MS, Los Alamos National Laboratory, Los Alamos, New Mexico.
Model Name: USGSMOC
Sponsor: USGS
Description: MOC is a two-dimensional model for the simulation of non-conservative solute transport in
saturated ground water systems. The model is both general in its applicability and flexible in its design.
Thus, it can be applied to a wide range of problems. It computes changes in the spatial concentration
distribution over time caused by convective transport, hydrodynamic dispersion, mixing or dilution from
recharge, and chemical reactions. The chemical reactions include first order irreversible rate reaction (such as
radioactive decay), reversible equilibrium controlled sorption with linear, Fruendlich or Langmuir isotherms,
and reversible equilibrium controlled ion exchange for monovalent or divalent ions. The model assumes that
fluid density variations, viscosity changes, and temperature gradients do not affect the velocity distribution.
MOC does allow modeling heterogeneous and/or anisotropic aquifers.
MOC couples the ground water flow equation with the non-conservative solute-transport equation. The
computer program uses the ADI or SIP procedure to solve the finite difference approximation of the ground
water flow equation. The SIP procedure for solving the ground water flow equation is most useful when areal
discontinuities in transmissivity exist or when the ADI solution does not converge. MOC uses the method of
characteristics to solve the solute transport equation. It uses a particle tracking procedure to represent
convective transport and a two-step explicit procedure to solve the finite difference equation that describes the
effects of hydrodynamic dispersion, fluid sources and sinks, and divergence of velocity. The explicit
procedure is subject to stability criteria, but the program automatically determines and implements the time
step limitations necessary to satisfy the stability criteria.
MOC uses a rectangular, block-centered, finite difference grid for flux and transport calculations. The grid
size for flow calculations is limited to 40 rows and 40 columns. The grid size for transport calculations is
limited to 20 rows and 20 columns which can be assigned to any area of the flow grid. The program allows
spatially varying diffuse recharge or discharge, saturated thickness, transmissivity, boundary conditions,
initial heads and initial concentrations and an unlimited number of injection or withdrawal wells. Up to five
nodes can be designated as observation points for which a summary table of head and concentration versus
time is printed at the end of the calculations.
An interactive preprocessor, PREMOC, is included with the program to facilitate user friendly data entry and
editing.
Reference: Konikow, L.F. and J.D. Brederhoft. 1978. Computer Model of Two-Dimensional Transport and
Dispersion in Ground Water. USGS. Techniques of Water Resource Investigation. Book 7. Chapter 2.
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Goode, D.J. and L.F Konikow. 1989 Modification of a Method-of-Charactenstics Solute Transport Model
to Incorporate Decay and Equilibrium-Controlled Sorption or Ion Exchange. USGS Water Resources
Investigations Report 89-4030.
Model Name: VAM2D (H.3D.3DCG)
Sponsor: Hydrogeologic Inc.
Description: VAM2D (NRC, 1989) is a finite element model that couples porous media water flow and
contaminant transport through the saturated and unsaturated zones. The code was developed for the NRC.
Specific features of the code and processes that the code is capable of simulating include:
Two dimensional flow and transport
Chain-decay transport
Dispersion
Retardation
Anisotropic and/or heterogeneous lithology
Confined and/or unconfmed aquifers
Aquitards
Steady state or transient conditions
Pulse and step releases from contaminated sources
Point, line or area! sources
There are a whole range of flow and transport processes that VAM2D cannot simulate including vapor
transport, complex geochemical reactions, three-dimensional fate and transport, and a variety of processes
that may be essential in the evaluation of selected remedial alternatives. However, these limitations would
generally not preclude the successful application of VAM2D to support the baseline risk assessment and
characterization program.
VAM2D has been extensively tested through the INTERVAL Program and has been applied at numerous sites
contaminated with radionuchdes including: Los Alamos, West Valley, and Maxey Flats.
Reference: Huyakom, P.S., 1989. VAM2D - Variably Saturated Analysis Model in Two Dimensions.
NUREGY/CR-53S2, Hydrogeologic Inc. for the U.S. Nuclear Regulatory Commission, Washington, DC.
Huyakom, P.S., White, H.O., Kool, J.B., and Buckley, J.E., 1988. VAN2DH Version 1.0: A Vanablv
Saturated Flow and Transport Analysis Model in 2-Dimensions. Documentation and User's Guide.
Hydrogeologic Inc., Hemdon, Virginia.
Huyakom, P.S., and Panday, S., 1990. VAM3DCG: Variable Saturated Analysis Model in Three
Dimensions with Preconditioned Comugate Matrix Solvers - Documentation and User's Manual. Version 2.0,
Hydrogeologic, Inc., Herndon, Virginia.
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GEOCHEMICAL/HYDROCHEMICAL
Model Name: BALANCE (-A)
Sponsor: USGS
Description: Hydrochemical model.
Reference: Parkhurst, D.L., L.N. Plummer and D.C. Thorstenson, 1982. BALANCE-A Computer Program
for Calculating Mass Transfer for Geochemical Reactions in Ground Water. U.S. Geological Survey, Water
Resources Investigations 82-0014, 33 pp.
Model Name: EQ3/6
Sponsor: USDOE
Description: Solute transport.
Reference: Wolery, T.J., Jackson, K.J., Boucier, W.L., Bruton, C.J., Viani, B.E., and Delany, J.M., 1988.
The EQ3/6 software package for geochemical modeling: Current status. American Chemical Society,
Division of Geochemistry, 196th ACS National Meeting, Los Angeles, California, Se[pt. 25-30 (abstract).
Wolery, T.J., et al., 1990. Current Status of the EO3/6 Software Package for Geochemical Modeling.
Chemical Modeling in Aqueous Systems II. D.C. Melchior and R.L. Basset, eds., ACS Symposium Series
416, American Chemical Society, Washington, D.C.
Model Name: HYDROGEOCHEM
Sponsor:
Description: Hydrochemical model
Reference: G.T. Yeh and V.S. Tripathi. Complete citation not provided by respondents.
Model Name: MINTEQ (Al)(Equilibnum Metal Speciation Model)
Sponsor: USEPA
Description: Geochemical model; calculates equilibrium aqueous speciation, adsorption, gas phase
partitioning, solid phase saturation states and precipitation-dissolution of eleven metals.
Reference: Brown, D.S. and J.D. Allison. 1987. MINTEOA1 Metal Speciation Model; A User's Manual.
EPA/600/3-87/012, USEPA, Athens, Georgia.
Felmy, A.R., D.C. Girvm and E.A. Jenne. 1984. MINTEO - A Program For Calculating Geochemical
Equilibria. EPA/600/3-84-032, USEPA, Athens Georgia.
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Model Name: PHREEQE
Sponsor: USGS
Description: PHREEQE is a FORTRAN IV computer program designed to model geochemical reactions.
Based on an ion pairing aqueous model, PHREEQE can calculate pH, redox potential, and mass transfer as a
function of reaction progress. The composition of solutions in equilibrium with multiple phases can be
calculated. The aqueous model, including elements, aqueous species, and mineral phases, is exterior to the
computer code and is completely user definable. PHREEQE can simulate several types of reactions including
(1) addition of reactants to a solution, (2) mixing of two waters, and (3) titrating one solution with another.
In each of these cases PHREEQE can simultaneously maintain the reacting solution at equilibrium with
multiple phase boundaries. The program calculates the following quantities during the reaction simulation:
1) pH;
2) pe;
3) total concentration of elements;
4) amounts of minerals (or other phases) transferred into or out of the aqueous phase;
5) distribution of aqueous species; and
6) saturation state of the aqueous phase with respect to specified mineral phases.
Reference: D.L. Parkhurst, D.C. Thorstenson and L.N. Plummer, 1980. PHREEOE - A Computer Program
for Geochemical Calculations. U.S. Geological Survey, Water-Resources Investigations 80-96, 209 pp.
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ENGINEERING/PERFORMANCE/ACCIDENT
Model Name: BARRIER
Sponsor: EPRI
Description: Simulates the long-term performance of low-level radioactive waste disposal facilities.
Predicts: long-term water balance; degradation of concrete structures over time and cracking and failure of
concrete structures.
BARRIER projects the failure of facility structural components and water flow through the facility prior to
and following failure. Unsaturated ground water flow modeling is based on Darcy's Law for water flow as
extended to unsaturated systems. Facility degradation is modeled mechanistically, employing concrete
deterioration and structural analysis algorithms pertinent to each facility design.
Reference: Shuman, R., V.C. Rogers, N. Chau and G.B. Merrel. 1989. The BARRIER Code: A Tool for
Estimating the Long-Term Performance of Low-Level Radioactive Waste Disposal Facilities.
NP-6218-CCML.
Model Name: BRUNZOG
Sponsor: US ARMY
Description: Calculates depth of thaw penetration.
Reference: Prepared by E.J. Chamberlin, U.S. Army Cold Regions Research and Engineering Laboratory.
Complete citation not provided by respondents.
Model Name: CONSOL
Sponsor: ?
Description: Calculates settlement.
Reference: Prepared by U.C. Berkeley. Complete citation not provided by respondents.
Model Name: HELP (Hydrologic Evaluation of Landfill Performance)
Sponsor: USEPA
Description: Estimates the amount of surface runoff, subsurface drainage and leachate that may result from
the operation of various landfill designs. The program models the effects of hydrologic processes including
precipitation, surface storage, runoff, infiltration, percolation, evapotranspiration, soil moisture storage, and
lateral drainage using a quasi-two-dimensional approach.
Reference: Schroeder, P.R., J.M. Morgan, T.M. Walski and A.C. Gibson. 1984. The Hvdrologic
Evaluation of Landfill Performance (HELP) Model. EPA/530-SW-84-009.
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Model Name: MACCS (Reactor Accident Consequence Analysis Code)
Sponsor: USNRC
Description: Estimates environmental concentrations, intakes, dose-equivalents and risks resulting from a
reactor accident.
Reference: Developed by Sandia National Laboratories. Complete citation not provided by respondents.
Model Name: ORIGEN2
Sponsor: RSIC
Description: ORIGEN2 is a revised and updated version of ORIGEN (Oak Ridge Isotope Generation).
ORJGEN2 performs a point-depletion calculation on reactor fuel, irradiation of reactor components, and
determines the composition, radiation, and spectra of any part of the fuel cycle. A matrix exponential
technique is applied to compute nuclide concentrations. In some cases the Bateman equation and secular
equilibrium are used. The cross sections are assumed to be constant, except for a number of key actinide
reactions that are varied with burnup. Nuclear libraries supplied with the code provide space and spectrum-
averaged cross-sections. One-group flux is assumed. Output values are used as source terms for radiation
exposure and radiation shielding codes.
Reference: Croff, A.G., 1980. A User's Manual for the ORIGEN2 Computer Code. ORNL/TM-7175
Model Name: PAGAN (Performance Assessment Ground Water Analysis of low-level Nuclear waste)
Sponsor: USNRC - SNL
Description: The PAGAN code is used to assess the performance of low-level waste and contains the
transport codes DISPERSE and SURFACE (Kozak et al., 1990). PAGAN calculates release from a source
using either a nnse-release or a leach-limited source-term model. This release term is used as an area source
into the aquifer at the water table, and radionuchde concentrations at various locations and times can be
calculated. If the contaminated aquifer also discharges into a surface water body, the flux of radionuclides
into the surface water can be calculated in a separate run of PAGAN. If the surface water body is a small
flowing nver, the radionuchde concentration in the nver may be calculated using a simple dilution factor in
PAGAN.
The surface and ground water capabilities of PAGAN have been incorporated into the GENII code (Napier et
al., 1988).
Reference: Chu, M.S.Y., Kozak, M.W., Campbell, J.E., and Thompson, B.M., 1991. A Selt-Teachinp
Curriculum for the NRC/SNL Low-Level Waste Performance Assessment Methodology. NUREG/CR-5539,
SAND90-Q585, U.S. Nuclear Regulatory Commission, Washington, D.C.
Model Name: PC-SLOPE
Sponsor: Geo-slope, Inc., commercial product
Description: Failure surface calculations.
Reference: Geo-Slope, Calgary Canada. Complete citation not provided by respondents.
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Model Name: RASCAL
Sponsor: USNRC
Description: Estimates dose-equivalents and health effects due to reactor accidents.
Reference: Model prepared by ORNL and Phoenix Associates Inc. Complete citation not provided by
respondents.
Model Name: RSAC (Radiological Safety Analysis Computer Program)
Sponsor: USDOE
Description: Evaluation of the impact of nuclear facilities, operation and accidents. The program can
calculate: fission product buildup and decay, meteorological diffusion and/or depletion values, and individual
or population doses resulting from inhalation, deposition or ingestion of or direct exposure to radionuclides
released to the environment.
Reference: Wenzel, D.R. 1982. RSAC-3: Radiological Safety Analysis Computer Program. ENICO-1002.
Exxon Nuclear Idaho Co., Inc., Idaho Falls.
Model Name: SFRIPD
Sponsor: MK Environmental
Description: Calculates safety factors for nprap sizing.
Reference: Developed'm-house by MK Environmental, San Francisco, California. Complete citation not
provided by respondents.
Model Name: SFRJPE
Sponsor: MK Environmental
Description: Calculates safety factors for riprap sizing.
Reference: Developed in-house by MK Environmental, San Francisco, California. Complete citation not
provided by respondents.
Model Name: STABL
Sponsor: Indiana
Description: Calculates failure surfaces, factors of safety ?
Reference: Prepared by R.A. Siegel, Purdue University, for the Indiana State Highway Commission.
Complete citation not provided by respondents.
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Model Name: STABLS
Sponsor: US DOT
Description: Calculates failure surfaces, factors of safety.
Reference: Prepared by Purdue University for The Joint Highway Research Project, Federal Highway
Administration, U.S. Department of Transportation. Complete citation not provided by respondents.
Model Name: STABR
Sponsor:
Description:
Reference: Prepared by U.C. Berkeley. Complete citation not provided by respondents.
Model Name: STEPH
Sponsor: MK Environmental
Description: Calculates riprap sizing.
Reference: Developed in-house by MK Environmental, San Francisco, California. Complete citation not
provided by respondents.
Model Name: UTEXAS2
Sponsor: Texas
Description: Calculates failure surfaces and factors of safety.
Reference: Prepared by Stephen G. Wright for the Texas State Department of Highways and Public
Transportation. Complete citation not provided by respondents..
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RADIATION DOSE
Model Name: ISOSHLD (-II)
Sponsor: USDOE
Description: ISOSHLD is used to calculate radiation dose at a point from bremsstrahlung and/or gamma rays
emitted from radioisotope sources. ISOSHLD-II is an extension of ISOSHLD with the added bremsstrahlung
mode. Five shield regions can be handled with up to twenty materials per shield region, the source is
considered to be the first shield region, i.e., bremsstrahlung and gamma rays are produced only in the source.
Point kernel integration (over the source region) is used to calculate the radiation doses at a field point.
Data needed to calculate fission-product isotopic concentrations, source spectrum distributions, and
attenuation coefficients are contained in libraries used by the code. Problem input data is thereby minimized;
and information required specifies the source-shield configuration and identifies the relevant materials and
their densities.
Reference: Engle, R.L., J. Greenborg and M.M. Hendrickson. 1966. ISOSHLD - A Computer Code For
General Purpose Isotope Shielding Analysis. BNWL-236. Pacific Northwest Laboratory, Richland,
Washington.
Simmons, G.L., J.I. Regimbal, J. Greenborg, E.L. Kelley, Jr., H.H. Van Tuyl. 1967. ISOSHLD-II: Code
Revision to Include calculation of Dose Rate From Shielded Bremsstrahlung Sources. BNWL-236
Supplement 1, Pacific Northwest Laboratory, Richland Washington.
Model Name: LADTAP
Sponsor: USNRC/Oak Ridge NL
Description:
Reference: Simpson, D.B., and McGill, 1980. Users' Manual for LADTAP II - A computer Program for
calculating radiation exposure to man from routine release of Nuclear Reactor Liquid Effluents. Oak Ridge
National Lab., Oak Ridge, TN, NUREG/CR-1276 (ORNL/NUREG/TOMC-1).
Model Name: RADRISK
Sponsor: USEPA
Description: Life-table methodology to derive dosimetric and health effects data. Often used with AIRDOS
and DARTAB.
Reference: Dunning, D.E., Jr., R.W. Leggett and M.G. Yalcintas. 1980. A Combined Methodology for
Estimating Dose Rates and Health Effects From Radioactive Pollutants. ORNL/TM-7105.
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UTILITIES
Model Name: SURFER
Sponsor: Golden Software
Description: 3-dimensional gnddmg, contounng and surface plotting software.
Reference: SURFER. Golden Software, Golden, CO.
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ACKNOWLEDGMENT
This project is coordinated by the Office of Radiation and Indoor Air, U.S.
Environmental Protection Agency, Washington D.C. and jointly funded by the
following organizations:
EPA Office of Radiation and Indoor Air (ORIA)
EPA Office of Solid Waste and Emergency Response (OSWER)
DOE Office of Environmental Restoration and Waste management (EM)
NRG Office of Nuclear Material Safety and Safeguards (ONMSS)
The project Steering Committee for this effort includes:
EPA
Beverly Irla, EPA/ORIA Work Assignment Manager
Lynn Deering, EPA/OSWER
Kung-Wei Yeh, EPA/ORIA
DOE
Ann Tallman, DOE/EM
Paul Beam, DOE/EM
NRG
Harvey Spiro, NRC/ONMSS
Contractors
Paul D. Moskowitz and Richard R. Pardi, Brookhaven National Laboratory
John Mauro, S. Cohen & Associates, Inc.
Consultants
Jim Rumbaugh, IJJ, Geraghty & Miller, Inc.
David Back, Hyrogeologic, Inc.
We acknowledge the technical support provided by these organizations and individuals. We
also thank all survey respondents and reviewers who helped make this report possible
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