&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 ------- 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 ------- 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. ------- 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 ------- 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 ------- 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 ------- 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 ------- 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 ------- 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 ------- 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. ------- 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: ------- 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) ------- 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 ------- 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. ------- 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. ------- 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, ------- Frequency of Respondent Site Type DOE DEFENSE EPA/SUPERFUND O C jo m to DOE UMTRA NRC DOE/NATL LAB DOE/SFMP DOE/FUSRAP ------- 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 ------- Frequency of Moa Js/Media Category Engineering Geochemical Ground Water Multi-Media Utilities Surface Water * Including Performance, Accident & Rad. Dose Models ------- 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+ ------- 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 ------- 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. ------- 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 ------- 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 ------- 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 ------- 7. REFERENCES Ahlstrom, S., Foote, H.P. 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Industrial Source Complex (ISO Dispersion Model User's Guide. EPA-45015-79-030. H.E. Cramer Co., Salt Lake City, Utah. 39 ------- Brode, R.W., 1988. Screening Procedures for estimating the air quality impact of stationary sources. EPA-450/4-88-010. Brown, D.S., and Allison, J.D., 1987. MINTEQA1 Metal Speciation Model: A User's Manual. EPA/600/3-87/012., U.S. EPA, Athens, Georgia. Campbell, I.E., Longsine, D.E., and Cranwell, R.M., 1981. Risk Methodlogv for Geologic Disposal of Radioactive Waste: the NWFT/DVM Computer Code User's Manual. NUREG/CR-2081, SAND81-0886. Campbell, J.E., and O'Neal, B.L., 1990. IMPACTS-BRC: The Microsoft Version. Proceedings of the Twenty-third Midyear Topical Symposium of the Health Physics Society, RISK: Perception. Assessment. Management, and Communication. February 5-8, 1990. Case, M.J., Maheras, M.D., Otis, M.D., and Baca, R.G., 1989. A Review and Selection of Computer Codes for Establishment of the Performance Assessment Center. 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University of Kentucky, July, 1975. Sullivan, T.M., and Suen, C.J., 1989. Low-level waste shallow land disposal source term model: Data input guides. Brookhaven National Lab BNL-NUREG-52206, USNRC, NUREG/CR-5387. Till, J.E., Meyer, K.R., and Moore, R.E., 1987. MICRQA1RDOS User's Manual and Documentation. Radiological Assessments Corporation, Neeses, South Carolina. Travis, B.J., 1982. WAFE: A Model for Two-phase Multi-component Mass and Heat Transport in Porous Chemically Active Media. Report LA-10488-MS, Los Alamos National Laboratory, Los Alamos, New Mexico. 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. TRC Environmental Consultants, 1987. ISCLT - Industrial Source Complex - Long Term. East Hartford Conn. TRC Environmental Consultants, 1987. ISCST - Industrial Source Complex - Short Term. East Hartford Conn. Trent, D.S., and Onishi, Y., 1989. Proceedings of the ASCE Speciality Conference: Estuarine and Coastal Circulation and Transport Modeling (FLESCOT). Model - Data Comparison. November 15-17, Newport, Rhode Island. Trent, D.S., Eyler, L.L., and Budden, M.J., 1983. TEMPEST-A Three-Pimensional Time-Dependent Computer Program for Hydrothermal Analysis. PNL-4348, 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. United States Geological Survey Book 7, Chapter Cl, Techniques of Water Resources Investigations of the United States Geological Survey, 116 pp. Truesdell, A.H., and Jones, B.F., 1974. WATEQ, a computer program for calculating chemical equilibria of natural waters. Journal of Research, U.S. Geological Survey, v. 2, p. 233-274. 54 ------- Tsang, T.W., and Tsang, C.F., 1987. Channel model of flow through fractured media. Water Resources Research, v. 23, p. 467-479. U.S. Army, Kunkel, B.A. 1988. Users Guide for the Air Force Toxic Chemical Dispersion Model - AFTOX. (AFGL-TR-88-0009, AF6L, Hanscon AFB, Maine, 1988. U.S. Department of Energy, Eslinger P.W. Engel D.W.,. Chamberlain P.J., 1992. SUMO-System Performance Assessment for High Level Nuclear Waste Repositoryy: Mathematical Models. (PNL7581, Pacific Northwest Laboritory, Richland, Washington. U.S. Environmental Protection Agency, 1989. COMPLY. EPA 520/1-89-003. U.S. Environmental Protection Agency, CAP-88. Radin Corporation, CHARM. U.S. Environmental Protection Agency, SCREEN. (U. S. Environmental Protection Agency, SIMS.) U.S. Army Corps of Engineers, 1981. HEC-1 Flood Hydrograph Package. User's Guide. U. S. Army Corps of Engineers, The Hydrologic Engineering Center. U.S. Army Corps of Engineers, 1982. HEC-2 Water Surface Profiles. User's Manual. U. S. Army Corps of Engineers, The Hydrologic Engineering Center. U.S. Department of Transportation, STABL5. Purdue University, The Joint Highway Research Project, Federal Highway Administration. Complete citation not available. U.S. Environmental Protection Agency, 1988. Superfund Exposure Assessment Manual. EPA/540/1-88/001, Office of Remedial Response, Washington, D.C. U.S. Environmental Protection Agency, 1989a. OSWER Models Study: Promoting Appropriate Use of Models in Hazardous Waste/Superfund Programs. Phase I Final Report. Information Management Staff, Office of Program Management and Technology, Office of Solid Waste and Emergency Response, Washington, D.C. U.S. Environmental Protection Agency, 1989b. Report of Task Group on Models. Prepared by Gordon Hurley, Science Advisor, Office of Radiation Programs for Richard Guimond, Director, Office of Radiation Programs, Washington, D.C. 55 ------- U.S. Environmental Protection Agency, 1989c. User's Guide for AIRDOS-PC. EPA 520/6-89-035, U.S. Environmental Protection Agency, Office of Radiation Programs, Las Vegas, Nevada. U.S. Nuclear Regulatory Commission, CONDOS-II. Univ. Calif, at Berkeley, CONSOL. Univ. Calif, at Berkeley, STABR. Voorhees, M.L., and Rice, J.L., InterTrans. Voss, C.I., 1984. AQUIFEM-SALT: A Finite-Element Model for Aquifers Containing a Seawater Interface. Water Resources Investigations Report 84-4263, U.S. Geological Survey, Reston, Virginia, 37 pp. 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. Water Resources Investigations Rep. 84-4369, U.S. Geological Survey, Reston, Virginia, 409 pp. Ward, D.S., Reeves, M., and Duda, L.E., 1984. Verification and field comparison of the Sandia Waste-Isolation Flow and Transport Model (SWIFT). Rep. SAND83-1154 and NUREG/CR-3316, Sandia National Laboratory, Albuquerque, N.M. Waterloo Hydrogeologic, FLOWPATM. Wenzel, D.R., 1982. RSAC-3: Radiological Safety Analysis Computer Program. EN1CO-1002. Exxon Nuclear Idaho Co., Inc., Idaho Falls. Westall, J.C., 1979. MICROQL:!: A Chemical Equilibrium Program in BASIC. EAWAG. Swiss Federal Institute of Technology, Duebendorf, Switzerland. Westall, J.C., Zachary, J.L., and Morel, F.M.M., 1976. MINEQL - A Computer Program for the Calculation of Chemical Equilibrium Composition of Aqueous Systems. Technical Note 18, R.M. Parsons Laboratory, Department of Civil Engineering, Massachusetts Institute of Technology, Cambridge, Massachusetts, 91pp. Whelan, G., Strenge, D.L., Droppo Jr., J.G., and Steelman, B.L., 1987. The Remedial Action Priority System (RAPS): Mathematical Formulations. PNL- 6200, Pacific Northwest Laboratory, Richland, Washington. 56 ------- Wigley, T.M.L., 1977. WATSPEC: a computer program for determining the equilibrium speciation of aqueous solutions. British Geomorphological Research Group Technical Bulletin, v. 20, 48 pp. Wilson, J., and Townley, L., 1980. AOU1FEM: Two-Pimensional Ground Water Flow Model. MIT Hydrodynamics Laboratory Report No. 248 and No. 252, Cambridge, MA. Yeh, G.T., 1981. AT123D: Analytical Transient One-, Two-, and Three-Dimensional Simulation of Waste Transport in the Aquifer System. ORNL-5602, Oak Ridge National Laboratory, Oak Ridge, Tenn. 83 pp. Wolery, T.J., and Walters, L.J., Jr., 1975. Calculation of equilibrium between aqueous solution and minerals: the EQ3/6 software package. National technical Information Service UCRL-52658. 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 Chemcial Society, Washington, D.C. Wright, S.C., 1992. UTEXAS2. Texas State Department of Highways and Public Transportation. Yeh, G.T., and Strand, R.H., 1982. FEMWATER: User's Manual of a Finite-Element Code for Simulating Water Flow Through Saturated-Unsaturated Porous Media. Oak Ridge National Laboratory, Oak Ridge Tennessee, ORNL/TM-7316. Yeh, G.T., and Ward, D.S., 1980. FEMWATER: A Finite Element Model of WATER Flow Through Saturated-Unsaturated Porous Media. Oak Ridge National Laboratory, Oak Ridge, Tennessee, ORNL-5567. Yeh, G.T., and Ward, D.S., 1981. FEMWASTE: A Finite Element Model of WASTE Transport Through Saturated-Unsaturated Porous Media. Oak Ridge National Laboratory, Oak Ridge, Tennessee, ORNL-5601. Yu, C., 1987. A Simulation Model for Analyzing the Environmental Impact of Waste Disposal Systems: MAT123D. Argonne National Laboratory, Illinois Yuan, Y.C., Wang, J.H.C., and Zielen, A., 1989. MILDOS-AREA: An Enhanced Version of MILDOS or Large Area Sources. ANL/ES-161. Argonne National Laboratory, Illinois. 57 ------- 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. Ken- Environmental Research Laboratory, Ada, OK. 58 ------- 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 59 ------- 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 60 ------- 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. 61 ------- 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. 62 ------- 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. 63 ------- 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. 64 ------- 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. 65 ------- 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. 66 ------- 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 67 ------- 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 68 ------- 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. 69 ------- 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. 70 ------- 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. 71 ------- 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. 72 ------- 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. 73 ------- 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 74 ------- 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. 75 ------- 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 76 ------- 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. 77 ------- 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; 78 ------- • 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. 79 ------- 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. 80 ------- 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. 81 ------- 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. 82 ------- 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. 83 ------- 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. 84 ------- 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) 85 ------- 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. 86 ------- 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: 87 ------- 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 88 ------- 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. 89 ------- 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 90 ------- 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 91 ------- 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. 92 ------- 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. 93 ------- 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. 94 ------- 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. 95 ------- 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. 96 ------- 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. 97 ------- 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. 98 ------- 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. 99 ------- 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.. 100 ------- 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. 101 ------- UTILITIES Model Name: SURFER Sponsor: Golden Software Description: 3-dimensional gnddmg, contounng and surface plotting software. Reference: SURFER. Golden Software, Golden, CO. 102 ------- 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 103 ------- |