-
2
-
-
0000686865
-
Code of federal regulations, title 10, chapter 1, part 61 "Licensing requirements for land disposal of radioactive waste,"
-
U.S. Nuclear Regulatory Commission, Code of federal regulations, title 10, chapter 1, part 61 "Licensing requirements for land disposal of radioactive waste," Fed. Registr. 47, 57446, 1982.
-
(1982)
Fed. Registr.
, vol.47
, pp. 57446
-
-
-
3
-
-
0008502092
-
-
15A NCAC 11, N.C. Department of Environment, Health, and Natural Resources, Division of Radiation Protection, July
-
North Carolina Regulations for Protection Against Radiation, 15A NCAC 11, N.C. Department of Environment, Health, and Natural Resources, Division of Radiation Protection, July, 1993.
-
(1993)
North Carolina Regulations for Protection Against Radiation
-
-
-
4
-
-
85031610592
-
Realizing more accurate waste characterization for disposal site dose risk assessment
-
Providence, RI, July 21-23
-
J. Cline, "Realizing more accurate waste characterization for disposal site dose risk assessment," 1997 EPRI International LLW Conference, Providence, RI, July 21-23, 1997.
-
(1997)
1997 EPRI International LLW Conference
-
-
Cline, J.1
-
5
-
-
0008487725
-
Performance assessment and LLW characterization
-
EPRI TR-107201, November
-
Electric Power Research Institute, "Performance assessment and LLW characterization," in Low Level Waste Characterization Guidelines, EPRI TR-107201, 2691, November 1996.
-
(1996)
Low Level Waste Characterization Guidelines
, pp. 2691
-
-
-
6
-
-
0008502093
-
-
CS-2434-CCM, Electric Power Research Institute
-
F. W. Bond, C. R. Cole, and P. J. Gutknecht, "Unsaturated Groundwater Flow Model (UNSAT1D) Computer Code Manual," CS-2434-CCM, Electric Power Research Institute, 1984.
-
(1984)
Unsaturated Groundwater Flow Model (UNSAT1D) Computer Code Manual
-
-
Bond, F.W.1
Cole, C.R.2
Gutknecht, P.J.3
-
7
-
-
0019057216
-
Calculating the unsaturated hydraulic conductivity with a new closed-form analytical model
-
Department of Civil Engineering, Princeton University, Princeton, NJ
-
M. Th. van Genuchten, "Calculating the unsaturated hydraulic conductivity with a new closed-form analytical model," Water Resource Program, Department of Civil Engineering, Princeton University, Princeton, NJ, 1978; "A closed-form equation for predicting the hydraulic conductivity of unsaturated soils," Soil Science Society of America Journal, Vol. 44 pp. 892-898, 1980.
-
(1978)
Water Resource Program
-
-
Van Genuchten, M.Th.1
-
8
-
-
0019057216
-
A closed-form equation for predicting the hydraulic conductivity of unsaturated soils
-
M. Th. van Genuchten, "Calculating the unsaturated hydraulic conductivity with anew closed-form analytical model," Water Resource Program, Department of Civil Engineering, Princeton University, Princeton, NJ, 1978; "A closed-form equation for predicting the hydraulic conductivity of unsaturated soils," Soil Science Society of America Journal, Vol. 44 pp. 892-898, 1980.
-
(1980)
Soil Science Society of America Journal
, vol.44
, pp. 892-898
-
-
-
9
-
-
0017469528
-
A comparison of numerical simulation models for one-dimensional infiltration
-
R. Haverkamp, M. Vaclin, J. Touma, P. J. Wierenga, and G. Vachaud, "A comparison of numerical simulation models for one-dimensional infiltration," Soil Science Society of America Journal, Vol. 41, pp. 285-294, 1977.
-
(1977)
Soil Science Society of America Journal
, vol.41
, pp. 285-294
-
-
Haverkamp, R.1
Vaclin, M.2
Touma, J.3
Wierenga, P.J.4
Vachaud, G.5
-
11
-
-
0020902413
-
A model to simulate infiltration of rainwater through the cover of a radioactive waste trench under saturated and unsaturated conditions
-
J. W. Mercer et al. (editors), Ann Arbor Science
-
C. Y. Hung, "A model to simulate infiltration of rainwater through the cover of a radioactive waste trench under saturated and unsaturated conditions," in Role of the Unsaturated Zone in Radioactive and Hazardous Waste Disposal, J. W. Mercer et al. (editors), Ann Arbor Science, 1983.
-
(1983)
Role of the Unsaturated Zone in Radioactive and Hazardous Waste Disposal
-
-
Hung, C.Y.1
-
12
-
-
0003578075
-
-
EPA/600/9-94/168, U. S. Environmental Protection Agency, Risk Reduction Engineering Laboratory
-
P. R. Schroeder, T. S. Dozier, P. A. Zappi, B. M. McEnroe, J. W. Sjostrom, and R. L. Peyton, "The Hydrologic Evaluation of Landfill Performance (HELP) Model: Engineering Documentation for Version 3," EPA/600/9-94/168, U. S. Environmental Protection Agency, Risk Reduction Engineering Laboratory, 1994.
-
(1994)
The Hydrologic Evaluation of Landfill Performance (HELP) Model: Engineering Documentation for Version 3
-
-
Schroeder, P.R.1
Dozier, T.S.2
Zappi, P.A.3
McEnroe, B.M.4
Sjostrom, J.W.5
Peyton, R.L.6
-
15
-
-
0003924783
-
-
NUREG/CR-5991, CNWRA 92-003, U.S. Nuclear Regulatory Commission
-
A. K. Runchal and B. Sagar, "PORFLOW: A Multifluid Multiphase Model for Simulating Flow, Heat Transfer, and Mass Transport in Fractured Porous Media, User's Manual - Version 2.41," NUREG/CR-5991, CNWRA 92-003, U.S. Nuclear Regulatory Commission, 1993.
-
(1993)
PORFLOW: A Multifluid Multiphase Model for Simulating Flow, Heat Transfer, and Mass Transport in Fractured Porous Media, User's Manual - Version 2.41
-
-
Runchal, A.K.1
Sagar, B.2
-
16
-
-
85031607807
-
-
NUREG/CR-6114, PNL-8842, U.S. Nuclear Regulatory Commission
-
P. D. Meyer, "Application of an Infiltration Evaluation Methodology to a Hypothetical Low-Level Waste Disposal Facility," NUREG/CR-6114, PNL-8842, Vol. 1, U.S. Nuclear Regulatory Commission, 1993.
-
(1993)
Application of an Infiltration Evaluation Methodology to a Hypothetical Low-Level Waste Disposal Facility
, vol.1
-
-
Meyer, P.D.1
-
17
-
-
0017558765
-
Solute distribution profiles computed with steady-state and transient water movement models
-
P. J. Wierenga, "Solute distribution profiles computed with steady-state and transient water movement models," Soil Science Society of America Journal, Vol. 41 pp. 1050-1055, 1977.
-
(1977)
Soil Science Society of America Journal
, vol.41
, pp. 1050-1055
-
-
Wierenga, P.J.1
-
18
-
-
0001544809
-
Solute transport through soil with adsorption and root water uptake computed with a transient and a constant-flux model
-
F. Beese and P. J. Wierenga, "Solute transport through soil with adsorption and root water uptake computed with a transient and a constant-flux model," Soil Science, Vol. 129, No. 4, pp. 245-252, 1980.
-
(1980)
Soil Science
, vol.129
, Issue.4
, pp. 245-252
-
-
Beese, F.1
Wierenga, P.J.2
-
19
-
-
0008441816
-
-
EPA 520/1-87-026, U.S. Environmental Protection Agency, December
-
V. Rogers and C. Hung, "PRESTO-EPA-CPG: A Low-Level Radioactive Waste Environmental Transport and Risk Assessment Code, Documentation and User's Manual," EPA 520/1-87-026, U.S. Environmental Protection Agency, December 1987.
-
(1987)
PRESTO-EPA-CPG: A Low-Level Radioactive Waste Environmental Transport and Risk Assessment Code, Documentation and User's Manual
-
-
Rogers, V.1
Hung, C.2
-
20
-
-
0003746359
-
-
NUREG/CR-5542, EGG-2597, U. S. Nuclear Regulatory Commission
-
J. C. Walton, L. E. Plansky, and R. W. Smith, "Models for Estimation of Service Life of Concrete Barriers in Low-Level Radioactive Waste Disposal," NUREG/CR-5542, EGG-2597, U. S. Nuclear Regulatory Commission, 1990.
-
(1990)
Models for Estimation of Service Life of Concrete Barriers in Low-Level Radioactive Waste Disposal
-
-
Walton, J.C.1
Plansky, L.E.2
Smith, R.W.3
-
22
-
-
85031614193
-
-
EPRI NO-7167-CCML, Electric Power Research Institute, May
-
R. Shuman, V. C. Rogers, N. Chau, and G. B. Merrell, "The BARRIER Code: A Tool for Estimating the Long-Term Performance of Low-Level Radioactive Waste Disposal Facilities," EPRI NO-7167-CCML, Electric Power Research Institute, May 1991.
-
(1991)
The BARRIER Code: A Tool for Estimating the Long-Term Performance of Low-Level Radioactive Waste Disposal Facilities
-
-
Shuman, R.1
Rogers, V.C.2
Chau, N.3
Merrell, G.B.4
-
24
-
-
0008524527
-
-
NUREG/CR-6070, EGG-2701, U.S. Nuclear Regulatory Commission
-
R. R. Seitz, and J. C. Walton, "Modeling Approaches for Concrete Barriers Used in Low-Level Waste Disposal," NUREG/CR-6070, EGG-2701, U.S. Nuclear Regulatory Commission, 1993.
-
(1993)
Modeling Approaches for Concrete Barriers Used in Low-Level Waste Disposal
-
-
Seitz, R.R.1
Walton, J.C.2
-
25
-
-
0008463790
-
Improved modeling of engineered barriers for low-level waste disposal
-
R. Shuman, N. Chau, and V. C. Rogers, "Improved modeling of engineered barriers for low-level waste disposal," Waste Management '91, Vol. 2, pp.757-762, 1991.
-
(1991)
Waste Management '91
, vol.2
, pp. 757-762
-
-
Shuman, R.1
Chau, N.2
Rogers, V.C.3
-
26
-
-
0022412914
-
Hydrologic mechanisms governing fluid flow in a partially saturated, fractured, porous medium
-
J. S. Y. Wang and T. N. Narasimhan, "Hydrologic mechanisms governing fluid flow in a partially saturated, fractured, porous medium," Water Resources Research, Vol. 21 (12), pp. 1861-1874, 1985.
-
(1985)
Water Resources Research
, vol.21
, Issue.12
, pp. 1861-1874
-
-
Wang, J.S.Y.1
Narasimhan, T.N.2
-
27
-
-
0027239054
-
Near-field performance assessment for the saltstone disposal facility
-
R. R. Seitz, J. C. Walton, C. A. Dicke, and C. S. Smith, "Near-field performance assessment for the saltstone disposal facility," Scientific Basis for Waste Management XVI, Materials Research Society Symposium Proceedings, Vol. 294, pp. 731-736, 1993.
-
(1993)
Scientific Basis for Waste Management XVI, Materials Research Society Symposium Proceedings
, vol.294
, pp. 731-736
-
-
Seitz, R.R.1
Walton, J.C.2
Dicke, C.A.3
Smith, C.S.4
-
28
-
-
0024165158
-
Seepage in a saturated-stratified aquifer with recharge
-
S. R. Yates, "Seepage in a saturated-stratified aquifer with recharge," Soil Science Society of America Journal, Vol. 52, pp. 356-363, 1988.
-
(1988)
Soil Science Society of America Journal
, vol.52
, pp. 356-363
-
-
Yates, S.R.1
-
33
-
-
0027152434
-
Experiments and modeling studies concerning localized corrosion of carbon steel and stainless steel containers for intermediate- and low-level radioactive waste
-
A. R. Hoch, C. C. Naish, S. M. Sharland, A. C. Smith, and K. J. Taylor, "Experiments and modeling studies concerning localized corrosion of carbon steel and stainless steel containers for intermediate- and low-level radioactive waste," Materials Research Society Symposium Proceedings, Vol. 294, 1993.
-
(1993)
Materials Research Society Symposium Proceedings
, vol.294
-
-
Hoch, A.R.1
Naish, C.C.2
Sharland, S.M.3
Smith, A.C.4
Taylor, K.J.5
-
34
-
-
85031604442
-
The assessment of localized corrosion of carbon and stainless steel containers for intermediate- and low-level radioactive waste under repository conditions
-
September 29 - October 2, 1991, Las Vegas, NV, American Nuclear Society
-
S. M. Sharland, G. P. Marsh, C. C. Naish, and K. J. Taylor, "The assessment of localized corrosion of carbon and stainless steel containers for intermediate- and low-level radioactive waste under repository conditions," Proc. of Topical Meeting on Nuclear Waste Packaging, Focus '91, September 29 - October 2, 1991, Las Vegas, NV, American Nuclear Society,1991.
-
(1991)
Proc. of Topical Meeting on Nuclear Waste Packaging, Focus '91
-
-
Sharland, S.M.1
Marsh, G.P.2
Naish, C.C.3
Taylor, K.J.4
-
35
-
-
85031608249
-
-
NUREG/CR-5453, SAND90-0375, U. S. Nuclear Regulatory Commission
-
M. W. Kozak, M S. Y. Chu, P. A. Mattingly, J. D. Johnson, and J. T. McCord, "Background Information for the Development of a Low-Level Waste Performance Assessment Methodology - Computer Code Implementation and Assessment," NUREG/CR-5453, SAND90-0375, Vol. 5, U. S. Nuclear Regulatory Commission, 1990.
-
(1990)
Background Information for the Development of a Low-Level Waste Performance Assessment Methodology - Computer Code Implementation and Assessment
, vol.5
-
-
Kozak, M.W.1
Chu, M.S.Y.2
Mattingly, P.A.3
Johnson, J.D.4
McCord, J.T.5
-
36
-
-
85031616223
-
Evaluation of uncertainties in low-level waste source term analysis
-
Salt Lake City, Utah, May 20-22
-
M. -S. Yim, "Evaluation of uncertainties in low-level waste source term analysis," Proceedings of the 18th DOE LLW Management Conference, Salt Lake City, Utah, May 20-22, 1997.
-
(1997)
Proceedings of the 18th DOE LLW Management Conference
-
-
Yim, M.-S.1
-
37
-
-
0008513912
-
-
NUREG/CR-5517, SAND89-3060, U.S. Nuclear Regulatory Commission
-
B. L. O'Neal and C. E. Lee, "IMPACTS-BRC, Version 2.0," NUREG/CR-5517, SAND89-3060, U. S. Nuclear Regulatory Commission, 1990; O. I. Oztunali and G. W. Roles, "Update of Part 61, Impacts Analysis Methodology," NUREG/CR-4370, U.S. Nuclear Regulatory Commission, 1986.
-
(1990)
IMPACTS-BRC, Version 2.0
-
-
O'Neal, B.L.1
Lee, C.E.2
-
38
-
-
0008487772
-
-
NUREG/CR-4370, U.S. Nuclear Regulatory Commission
-
B. L. O'Neal and C. E. Lee, "IMPACTS-BRC, Version 2.0," NUREG/CR-5517, SAND89-3060, U. S. Nuclear Regulatory Commission, 1990; O. I. Oztunali and G. W. Roles, "Update of Part 61, Impacts Analysis Methodology," NUREG/CR-4370, U.S. Nuclear Regulatory Commission, 1986.
-
(1986)
Update of Part 61, Impacts Analysis Methodology
-
-
Oztunali, O.I.1
Roles, G.W.2
-
40
-
-
85031609225
-
-
NUREG-0782, U. S. Nuclear Regulatory Commission
-
U. S. Nuclear Regulatory Commission, "Draft Environmental Impact Statement on 10CFR Part 61," NUREG-0782, Vol. 4, U. S. Nuclear Regulatory Commission, 1981.
-
(1981)
Draft Environmental Impact Statement on 10CFR Part 61
, vol.4
-
-
-
42
-
-
27844517981
-
Overview of NRC staff LLWPA modeling efforts
-
Rockville, MD, November 17
-
U. S. Nuclear Regulatory Commission, "Overview of NRC staff LLWPA modeling efforts," Low-Level Waste Performance Assessment Workshop, Rockville, MD, November 17, 1994.
-
(1994)
Low-Level Waste Performance Assessment Workshop
-
-
-
43
-
-
0008523130
-
-
NUREG/CR-5618, SAND90-2089, U. S. Nuclear Regulatory Commission
-
N. E. Olague, D. E. Longsine, J. E. Campbell, C. D. Leigh, "User's Manual for the NEFTRAN II Computer Code," NUREG/CR-5618, SAND90-2089, U. S. Nuclear Regulatory Commission, 1991.
-
(1991)
User's Manual for the NEFTRAN II Computer Code
-
-
Olague, N.E.1
Longsine, D.E.2
Campbell, J.E.3
Leigh, C.D.4
-
44
-
-
85031607904
-
-
NUREG/CR-6305, U. S. Nuclear Regulatory Commission
-
R. J. McKinnon, T. M. Sullivan, C. J. Suen, and S. A. Simonson, "BLT-EC (Breach, Leach, Transport, and Equilibrium Chemistry), a Finite-Element Model for Assessing the Release of Radionuclides from Low-Level Waste Disposal Units: Background, Theory, and Model Description," NUREG/CR-6305, U. S. Nuclear Regulatory Commission, 1995.
-
(1995)
BLT-EC (Breach, Leach, Transport, and Equilibrium Chemistry), a Finite-Element Model for Assessing the Release of Radionuclides from Low-Level Waste Disposal Units: Background, Theory, and Model Description
-
-
McKinnon, R.J.1
Sullivan, T.M.2
Suen, C.J.3
Simonson, S.A.4
-
46
-
-
85031614315
-
-
NUREG/CR-6492, BNL-NUREG-52509
-
T. M. Sullivan, R. J. MacKinnon, R. R. Kinsey, A. Aronson, and M. Divadeenam, "BLT-MS (Breach, Leach and Transport - Multiple Species) Data Input Guide: A Computer Model for Simulating Release of Contaminant from Subsurface Low-Level Waste Disposal Facility," NUREG/CR-6492, BNL-NUREG-52509, 1996.
-
(1996)
BLT-MS (Breach, Leach and Transport - Multiple Species) Data Input Guide: A Computer Model for Simulating Release of Contaminant from Subsurface Low-Level Waste Disposal Facility
-
-
Sullivan, T.M.1
MacKinnon, R.J.2
Kinsey, R.R.3
Aronson, A.4
Divadeenam, M.5
-
47
-
-
58349101069
-
-
Technical Branch, Division of Low-Level Waste Management and Decommissioning
-
U. S. Nuclear Regulatory Commission, Technical Position on Waste Form (Rev. 1), Technical Branch, Division of Low-Level Waste Management and Decommissioning, 1991.
-
(1991)
Technical Position on Waste Form (Rev. 1)
-
-
-
48
-
-
0004065851
-
-
Topical Report, NUREG/CR-4756, BNL/NUREG-52026, Brookhaven National Laboratory
-
H. Arora and R. Dayal, "Leaching Studies of Cement-Based Low-Level Radioactive Waste Forms," Topical Report, NUREG/CR-4756, BNL/NUREG-52026, Brookhaven National Laboratory, 1986.
-
(1986)
Leaching Studies of Cement-Based Low-Level Radioactive Waste Forms
-
-
Arora, H.1
Dayal, R.2
-
49
-
-
0029413259
-
Equilibrium concentration and diffusion controlled leaching model for cement-based waste forms
-
C. L. Kim, C. H. Cho, and H. J. Choi, "Equilibrium concentration and diffusion controlled leaching model for cement-based waste forms," Waste Management, Vol. 15 (5/6), 449-455, 1995.
-
(1995)
Waste Management
, vol.15
, Issue.5-6
, pp. 449-455
-
-
Kim, C.L.1
Cho, C.H.2
Choi, H.J.3
-
50
-
-
0030655583
-
Development of a new mechanistic low-level waste source term model
-
M.-S. Yim, "Development of a new mechanistic low-level waste source term model," Scientific Basis for Nuclear Waste Management XX, Mat. Res. Soc. Symp., Vol. 465, pp. 1059-1066, 1997.
-
(1997)
Scientific Basis for Nuclear Waste Management XX, Mat. Res. Soc. Symp.
, vol.465
, pp. 1059-1066
-
-
Yim, M.-S.1
-
53
-
-
0024731108
-
Leaching from solidified waste forms under saturated and unsaturated conditions
-
S. B. Oblath, "Leaching from solidified waste forms under saturated and unsaturated conditions," Environmental Science and Technology, Vol. 23, pp. 1098-1102, 1989.
-
(1989)
Environmental Science and Technology
, vol.23
, pp. 1098-1102
-
-
Oblath, S.B.1
-
54
-
-
0008487735
-
Leaching and migration of low-level wastes under unsaturated conditions
-
G. G. Eichholz, M. F. Petelka, and J. Whang, "Leaching and migration of low-level wastes under unsaturated conditions," Radioactive Waste Management and the Nuclear Fuel Cycle, Vol. 14, pp. 285-310, 1990.
-
(1990)
Radioactive Waste Management and the Nuclear Fuel Cycle
, vol.14
, pp. 285-310
-
-
Eichholz, G.G.1
Petelka, M.F.2
Whang, J.3
-
59
-
-
85031604021
-
-
NUREG/CR-5453, SAND89-2509, U. S. Nuclear Regulatory Commission
-
M. W. Kozak, C. P. Harlan, M. S. Y. Chu, and B. L. O'Neal, "Background Information for the Development of a Low-Level Waste Performance Assessment Methodology - Selection and Integration of Models," NUREG/CR-5453, SAND89-2509, Vol. 3, U. S. Nuclear Regulatory Commission, 1989.
-
(1989)
Background Information for the Development of a Low-Level Waste Performance Assessment Methodology - Selection and Integration of Models
, vol.3
-
-
Kozak, M.W.1
Harlan, C.P.2
Chu, M.S.Y.3
O'Neal, B.L.4
-
62
-
-
0019727189
-
Contaminant transport in fractured porous media: Analytical solution for a single fracture
-
D. H. Tang, E. O. Frind, and E. A. Sudicky, "Contaminant transport in fractured porous media: Analytical solution for a single fracture," Water Resources Research, Vol. 17, No. 3, pp. 555-564, 1981.
-
(1981)
Water Resources Research
, vol.17
, Issue.3
, pp. 555-564
-
-
Tang, D.H.1
Frind, E.O.2
Sudicky, E.A.3
-
63
-
-
0020330875
-
Contaminant transport in fractured porous media: Analytical solutions for a system of parallel fractures
-
E. A. Sudicky and E. O. Frind, "Contaminant transport in fractured porous media: analytical solutions for a system of parallel fractures," Water Resources Research, Vol. 18, No. 6, pp. 1634-1642, 1982.
-
(1982)
Water Resources Research
, vol.18
, Issue.6
, pp. 1634-1642
-
-
Sudicky, E.A.1
Frind, E.O.2
-
65
-
-
85031598676
-
-
NUREG/CR-5927, SAND91-2802, U. S. Nuclear Regulatory Commission
-
M. W. Kozak, N. E. Olague, R. R. Rao, and J. T. McCord, "Evaluation of a Performance Assessment Methodology for Low-Level Radioactive Waste Disposal Facilities," NUREG/CR-5927, SAND91-2802, Vol. 1, U. S. Nuclear Regulatory Commission, 1993.
-
(1993)
Evaluation of a Performance Assessment Methodology for Low-Level Radioactive Waste Disposal Facilities
, vol.1
-
-
Kozak, M.W.1
Olague, N.E.2
Rao, R.R.3
McCord, J.T.4
-
66
-
-
0008465919
-
-
NUREG/CR-5532, SAND90-0375, U. S. Nuclear Regulatory Commission
-
M. W. Kozak, M. S. Y. Chu, and P. A. Mattingly, "A Performance Assessment Methodology for Low-Level Waste Facilities;" NUREG/CR-5532, SAND90-0375, U. S. Nuclear Regulatory Commission, 1990.
-
(1990)
A Performance Assessment Methodology for Low-Level Waste Facilities
-
-
Kozak, M.W.1
Chu, M.S.Y.2
Mattingly, P.A.3
-
69
-
-
85031610552
-
-
Office of Solid Waste and Emergency Response, U. S. Environmental Protection Agency
-
U. S. Environmental Protection Agency, "Assessment Framework for Ground-Water Model Applications (Draft)," Office of Solid Waste and Emergency Response, U. S. Environmental Protection Agency, 1992.
-
(1992)
Assessment Framework for Ground-Water Model Applications (Draft)
-
-
-
70
-
-
0008428008
-
A conceptual framework for ground-water solute-transport studies with emphasis on physical mechanisms of solute movement
-
T. E. Reilly, O. L. Franke, H. T. Buxton, and G. D. Bennett, "A conceptual framework for ground-water solute-transport studies with emphasis on physical mechanisms of solute movement," U. S. Geological Survey Water-Resources Investigations Report 87-4191, 1987.
-
(1987)
U. S. Geological Survey Water-Resources Investigations Report 87-4191
-
-
Reilly, T.E.1
Franke, O.L.2
Buxton, H.T.3
Bennett, G.D.4
-
71
-
-
27144558856
-
-
EPA/600/2-89/045, Robert S. Kerr Environmental Research Laboratory, U. S. Environmental Protection Agency, Ada, OK
-
J. Weaver, C. G. Enfield, S. Yates, D. Kreamer, and C. White, "Predicting Subsurface Contaminant Transport and Transformation: Considerations for Model Selection and Field Validation," EPA/600/2-89/045, Robert S. Kerr Environmental Research Laboratory, U. S. Environmental Protection Agency, Ada, OK, 1989.
-
(1989)
Predicting Subsurface Contaminant Transport and Transformation: Considerations for Model Selection and Field Validation
-
-
Weaver, J.1
Enfield, C.G.2
Yates, S.3
Kreamer, D.4
White, C.5
-
73
-
-
0004036048
-
-
EPA/600/R-93/011, U. S. Environmental Protection Agency, Ada, OK
-
P. K. M. van der Heijde and O. A. Elnawawy, "Quality Assurance and Quality Control in the Development and Application of Ground-Water Models," EPA/600/R-93/011, U. S. Environmental Protection Agency, Ada, OK, 1992.
-
(1992)
Quality Assurance and Quality Control in the Development and Application of Ground-Water Models
-
-
Van der Heijde, P.K.M.1
Elnawawy, O.A.2
-
77
-
-
0008521915
-
-
PNL-6029, Pacific Northwest Laboratory
-
C. S. Simmons, C. T. Kincaid, and A. E, Reisenauer, "A Simplified Model for Radioactive Contaminant Transport: The TRNSS Code," PNL-6029, Pacific Northwest Laboratory, 1986.
-
(1986)
A Simplified Model for Radioactive Contaminant Transport: The TRNSS Code
-
-
Simmons, C.S.1
Kincaid, C.T.2
Reisenauer, A.E.3
-
78
-
-
0008442509
-
-
NUREG/CR-5352, HGL/89-01, U. S. Nuclear Regulatory Commission
-
P. S. Huyakorn, J. B. Kool, and J. B. Robertson, "Documentation and User's Guide: VAM2D - Variably Saturated Analysis Model in Two Dimensions," NUREG/CR-5352, HGL/89-01, U. S. Nuclear Regulatory Commission, 1989.
-
(1989)
Documentation and User's Guide: VAM2D - Variably Saturated Analysis Model in Two Dimensions
-
-
Huyakorn, P.S.1
Kool, J.B.2
Robertson, J.B.3
-
79
-
-
0003967942
-
Documentation of computer program VS2D to solve the equations of fluid flow in variably saturated porous media
-
U. S. Geological Survey
-
E. G. Lappala, R. W. Healy, and E. P. Weeks, "Documentation of computer program VS2D to solve the equations of fluid flow in variably saturated porous media," Water Resources Investigation Report 83-4099, U. S. Geological Survey, 1987.
-
(1987)
Water Resources Investigation Report 83-4099
-
-
Lappala, E.G.1
Healy, R.W.2
Weeks, E.P.3
-
80
-
-
0003869518
-
Simulation of solute transport in variably saturated porous media with supplemental information on modifications to the U.S. geological survey's computer program VS2D
-
U.S. Geological Survey
-
R. W. Healy, "Simulation of solute transport in variably saturated porous media with supplemental information on modifications to the U.S. geological survey's computer program VS2D," Water Resources Investigation Report 90-4025, U.S. Geological Survey, 1990.
-
(1990)
Water Resources Investigation Report 90-4025
-
-
Healy, R.W.1
-
84
-
-
0003967936
-
Documentation of computer programs to compute and display pathlines using results from the U.S. geological survey modular three-dimensional finite-difference ground-water flow model
-
D. W. Pollock, "Documentation of computer programs to compute and display pathlines using results from the U.S. geological survey modular three-dimensional finite-difference ground-water flow model," U.S. Geological Survey Open File Report 89-381, 1989.
-
(1989)
U.S. Geological Survey Open File Report 89-381
-
-
Pollock, D.W.1
-
86
-
-
0003871749
-
A finite-element simulation model for saturated-unsaturated fluid-density-dependent ground water flow with energy transport or chemically-reactive single-species solute transport
-
C. I. Voss, "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 Water-Resource Investigations Report 84-4369, 1984.
-
(1984)
U.S. Geological Survey Water-Resource Investigations Report 84-4369
-
-
Voss, C.I.1
-
88
-
-
84990643232
-
-
RHO-CR-143 P, Rockwell Hanford Operations
-
R. L. England, N. W. Kline, K. J. Ekblad, and R. G. Baca, "Magnum-2D Computer Code: User's Guide," RHO-CR-143 P, Rockwell Hanford Operations, 1986.
-
(1986)
Magnum-2D Computer Code: User's Guide
-
-
England, R.L.1
Kline, N.W.2
Ekblad, K.J.3
Baca, R.G.4
-
89
-
-
84990643232
-
-
RHO-CR-144 P, Rockwell Hanford Operations
-
N. W. Kline, R. L. England, and R. G. Baca, "CHAINT Computer Code: User's Guide," RHO-CR-144 P, Rockwell Hanford Operations, 1986.
-
(1986)
CHAINT Computer Code: User's Guide
-
-
Kline, N.W.1
England, R.L.2
Baca, R.G.3
-
90
-
-
0003438254
-
-
Golder Associates Inc.
-
W. Dershowitz, G. Lee, J. Geier, T. Foxford, and P. LaPointe, "Fracman Interactive Discrete Fracture Data Analysis, Geometric Modeling and Exploration Simulation: User Documentation Version 2.6," Golder Associates Inc., 1997.
-
(1997)
Fracman Interactive Discrete Fracture Data Analysis, Geometric Modeling and Exploration Simulation: User Documentation Version 2.6
-
-
Dershowitz, W.1
Lee, G.2
Geier, J.3
Foxford, T.4
LaPointe, P.5
-
92
-
-
85031607092
-
-
Personal Communications, Chem-Nuclear Systems, Inc.
-
Personal Communications, J. W. Latham, Chem-Nuclear Systems, Inc., 1996.
-
(1996)
-
-
Latham, J.W.1
-
93
-
-
0003910473
-
-
NUREG-0868, U.S. Nuclear Regulatory Commission
-
R. B. Codell, K. T. Key, and G. Whelan, "A Collection of Mathematical Models for Dispersion in Surface Water and Groundwater," NUREG-0868, U.S. Nuclear Regulatory Commission, 1982.
-
(1982)
A Collection of Mathematical Models for Dispersion in Surface Water and Groundwater
-
-
Codell, R.B.1
Key, K.T.2
Whelan, G.3
-
94
-
-
85031612035
-
-
Personal Communications, Department of Marine, Earth, and Atmospheric Science, North Carolina State University
-
Personal Communications, D. Evans, Department of Marine, Earth, and Atmospheric Science, North Carolina State University, 1997.
-
(1997)
-
-
Evans, D.1
-
95
-
-
85031611744
-
-
NUREG/CR-5453, SAND89-2509, U.S. Nuclear Regulatory Commission
-
L. R. Shipers and C. P. Harlan, "Background Information for the Development of a Low-Level Waste Performance Assessment Methodology," NUREG/CR-5453, SAND89-2509, Vol. 2, U.S. Nuclear Regulatory Commission, 1989.
-
(1989)
Background Information for the Development of a Low-Level Waste Performance Assessment Methodology
, vol.2
-
-
Shipers, L.R.1
Harlan, C.P.2
-
98
-
-
0003717001
-
-
ORNL-5532, Oak Ridge National Laboratory
-
R. E. Moore, C. F. Baes, L. M. McDowell-Boyer, A. P. Watson, F. O. Hoffman, J. C. Pleasant, and C. W. Miller, "AIRDOS-EPA: A Computerized Methodology for Estimating Environmental Concentrations and Dose to Man from Airborne Releases of Radionuclides," ORNL-5532, Oak Ridge National Laboratory, 1979.
-
(1979)
AIRDOS-EPA: A Computerized Methodology for Estimating Environmental Concentrations and Dose to Man from Airborne Releases of Radionuclides
-
-
Moore, R.E.1
Baes, C.F.2
McDowell-Boyer, L.M.3
Watson, A.P.4
Hoffman, F.O.5
Pleasant, J.C.6
Miller, C.W.7
-
99
-
-
0008488145
-
-
NUREG/CR-2919, PNL-4380
-
J. F. Sagendorf, J. T. Goll, and W. F. Sandusky, "XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations," NUREG/CR-2919, PNL-4380, 1982.
-
(1982)
XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations
-
-
Sagendorf, J.F.1
Goll, J.T.2
Sandusky, W.F.3
-
102
-
-
85031607699
-
-
PNL-6584, Pacific Northwest Laboratory
-
B. A. Napier, D. L. Strenge, R. A. Peloquin, and J. V. Ramsdell, "GENII - The Hanford Environmental Radiation Dosimetry Software System," PNL-6584 Vol. 1 & 2, Pacific Northwest Laboratory, 1988.
-
(1988)
GENII - The Hanford Environmental Radiation Dosimetry Software System
, vol.1-2
-
-
Napier, B.A.1
Strenge, D.L.2
Peloquin, R.A.3
Ramsdell, J.V.4
-
103
-
-
0003645244
-
-
NUREG/CR-3332, ORNL-5968, U. S. Nuclear Regulatory Commission
-
J. E. Till and H. R. Meyer, "Radiological Assessment, A Textbook on Environmental Dose Analysis," NUREG/CR-3332, ORNL-5968, U. S. Nuclear Regulatory Commission, 1983.
-
(1983)
Radiological Assessment, A Textbook on Environmental Dose Analysis
-
-
Till, J.E.1
Meyer, H.R.2
-
104
-
-
0008487741
-
-
NUREG/CR-4013, PNL-5270, U.S. Nuclear Regulatory Commission
-
D. L. Strenge, R. A. Peloquin, and G. Whelan, "LADTAP II - Technical Reference and User Guide," NUREG/CR-4013, PNL-5270, U.S. Nuclear Regulatory Commission, 1986.
-
(1986)
LADTAP II - Technical Reference and User Guide
-
-
Strenge, D.L.1
Peloquin, R.A.2
Whelan, G.3
-
105
-
-
10544232682
-
Calculation of annual doses to man from routine releases of reactor effluents for the purpose of evaluating compliance with 10 CFR part 50, appendix I
-
Revision 1
-
U. S. Nuclear Regulatory Commission, "Calculation of annual doses to man from routine releases of reactor effluents for the purpose of evaluating compliance with 10 CFR part 50, appendix I," Regulatory Guide 1.109, Revision 1, 1977.
-
(1977)
Regulatory Guide 1.109
-
-
-
107
-
-
0003418991
-
-
ANL/EAD/LD-2, Environmental Assessment Division, Argonne National Laboratory
-
C. Yu, A. J. Zielen, J.-J. Cheng, Y. C. Yuan, L. G. Jones, D. J. LePoire, Y. Y. Wang, C. O. Loureiro, E. Gnanapragasam, E. Faillace, A. Wallo III, W. A. Williams, and H. Peterson, "Manual for Implementing Residual Radioactive Material Guidelines Using RESRAD," Version 5.0, ANL/EAD/LD-2, Environmental Assessment Division, Argonne National Laboratory, 1993.
-
(1993)
"Manual for Implementing Residual Radioactive Material Guidelines Using RESRAD," Version 5.0
-
-
Yu, C.1
Zielen, A.J.2
Cheng, J.-J.3
Yuan, Y.C.4
Jones, L.G.5
LePoire, D.J.6
Wang, Y.Y.7
Loureiro, C.O.8
Gnanapragasam, E.9
Faillace, E.10
Wallo A. III11
Williams, W.A.12
Peterson, H.13
-
108
-
-
0004307329
-
-
SAND91-0561, Sandia National Laboratories
-
C. D. Leigh, B. M. Thompson, J. E. Campbell, D. E. Longsine, R. A. Kennedy, and B. A. Napier," User's Guide for GENII-S: A Code for Statistical and Deterministic Simulations of Radiation Doses to Humans from Radionuclides in the Environment," SAND91-0561, Sandia National Laboratories, 1992.
-
(1992)
User's Guide for GENII-S: A Code for Statistical and Deterministic Simulations of Radiation Doses to Humans from Radionuclides in the Environment
-
-
Leigh, C.D.1
Thompson, B.M.2
Campbell, J.E.3
Longsine, D.E.4
Kennedy, R.A.5
Napier, B.A.6
-
109
-
-
0008432490
-
-
PNL-10395, Pacific Northwest Laboratory
-
J. W. Buck, G. Whelan, J. G. Droppo, D. L. Strenge, K. J. Castleton, J. P. McDonald, C. Sato, and G. P. Streile, "Multimedia Environmental Pollutant Assessment System (MEPAS) Application Guidance, Guidelines for Evaluating MEPAS Input Parameters for Version 3.2," PNL-10395, Pacific Northwest Laboratory, 1995.
-
(1995)
Multimedia Environmental Pollutant Assessment System (MEPAS) Application Guidance, Guidelines for Evaluating MEPAS Input Parameters for Version 3.2
-
-
Buck, J.W.1
Whelan, G.2
Droppo, J.G.3
Strenge, D.L.4
Castleton, K.J.5
McDonald, J.P.6
Sato, C.7
Streile, G.P.8
-
110
-
-
0003618858
-
-
ICRP Publication 30, Part 1, Pergamon Press, New York
-
ICRP 30, Limits for Intakes of Radionuclides by Workers, ICRP Publication 30, Part 1, Pergamon Press, New York, 1982.
-
(1982)
Limits for Intakes of Radionuclides by Workers
-
-
-
112
-
-
0030407743
-
A probabilistic approach to quantify the uncertainties in internal dose assessment using response surface and neural network
-
ASME
-
M. Baek, S. K. Lee, U. C. Lee, and C. S. Kang, "A probabilistic approach to quantify the uncertainties in internal dose assessment using response surface and neural network," International Conference on Nuclear Engineering, Vol. 3, pp. 361-373, ASME, 1996.
-
(1996)
International Conference on Nuclear Engineering
, vol.3
, pp. 361-373
-
-
Baek, M.1
Lee, S.K.2
Lee, U.C.3
Kang, C.S.4
-
113
-
-
85031602047
-
-
Palisade Corporation, @RISK, 1-800-432-7475, New Field, NY
-
Palisade Corporation, @RISK, 1-800-432-7475, New Field, NY.
-
-
-
-
115
-
-
85031612656
-
-
Private Communications, U. S. Nuclear Regulatory Commission
-
Private Communications, U. S. Nuclear Regulatory Commission, 1996.
-
(1996)
-
-
-
116
-
-
85031603462
-
Treatment of uncertainty in low-level waste performance assessment
-
Atlanta, GA, November 19-21
-
M. W. Kozak, N. E. Olague, D. P. Gallegos, and R. R. Rao, "Treatment of uncertainty in low-level waste performance assessment," Proceedings of the 13th DOE LLW Management Conference, Atlanta, GA, November 19-21, 1991.
-
(1991)
Proceedings of the 13th DOE LLW Management Conference
-
-
Kozak, M.W.1
Olague, N.E.2
Gallegos, D.P.3
Rao, R.R.4
-
118
-
-
0019748016
-
Methods for uncertainty analysis: A comparative survey
-
D. C. Cox and P. Baybutt, "Methods for uncertainty analysis: A comparative survey," Risk Analysis, Vol. 1, No. 4, pp. 251-258, 1981.
-
(1981)
Risk Analysis
, vol.1
, Issue.4
, pp. 251-258
-
-
Cox, D.C.1
Baybutt, P.2
-
120
-
-
0025681550
-
The concept of probability in safety assessments of technological systems
-
G. E. Apostolakis, "The concept of probability in safety assessments of technological systems," Science, 250, pp. 1359-1364, 1990.
-
(1990)
Science
, vol.250
, pp. 1359-1364
-
-
Apostolakis, G.E.1
-
121
-
-
0342578829
-
A commentary on model uncertainty
-
A Mosleh, N. Siu, C. Smidts and C. Lui (eds.), NUREG/CP-0138, U.S. Nuclear Regulatory Commission, Annapolis, MD, Oct. 20-22
-
G. E. Apostolakis, "A commentary on model uncertainty," Proceedings of Workshop I on Advanced Topics in Risk and Reliability Analysis, A Mosleh, N. Siu, C. Smidts and C. Lui (eds.), NUREG/CP-0138, U.S. Nuclear Regulatory Commission, Annapolis, MD, Oct. 20-22, 1993.
-
(1993)
Proceedings of Workshop I on Advanced Topics in Risk and Reliability Analysis
-
-
Apostolakis, G.E.1
-
122
-
-
0008521916
-
Model uncertainty: Probabilities for models?
-
A Mosleh, N. Siu, C. Smidts and C. Lui (eds.), NUREG/CP-0138, U.S. Nuclear Regulatory Commission, Annapolis, MD, Oct. 20-22
-
R. L. Winkler, "Model uncertainty: Probabilities for models?", Proceedings of Workshop I on Advanced Topics in Risk and Reliability Analysis, A Mosleh, N. Siu, C. Smidts and C. Lui (eds.), NUREG/CP-0138, U.S. Nuclear Regulatory Commission, Annapolis, MD, Oct. 20-22/1993.
-
(1993)
Proceedings of Workshop I on Advanced Topics in Risk and Reliability Analysis
-
-
Winkler, R.L.1
-
123
-
-
85031609465
-
Towards a quantitative treatment of model uncertainty in the performance assessment of high-level radioactive waste repositories
-
Tucson, Arizona
-
E. Zio, G. E. Apostolakis, D. Okrent, "Towards a quantitative treatment of model uncertainty in the performance assessment of high-level radioactive waste repositories," Proceedings of WM'95, Tucson, Arizona, 1995.
-
(1995)
Proceedings of WM'95
-
-
Zio, E.1
Apostolakis, G.E.2
Okrent, D.3
-
125
-
-
85031608370
-
Quantitative analysis of model uncertainty: Estimating the credibility of alternate model structures
-
American Nuclear Society, Park City, UT, September 29 - October 3
-
E. Zio, "Quantitative analysis of model uncertainty: Estimating the credibility of alternate model structures," Proceedings of the International Topical Meeting on Probabilistic Safety Assessment, PSA'96, Pp. 1219-1226, American Nuclear Society, Park City, UT, September 29 - October 3, 1996.
-
(1996)
Proceedings of the International Topical Meeting on Probabilistic Safety Assessment, PSA'96
, pp. 1219-1226
-
-
Zio, E.1
-
126
-
-
0003494914
-
-
NUREG/CR-5211, SAND88-2703, U. S. Nuclear Regulatory Commission
-
P. Davis, E. J. Bonano, K. K. Wahi and L. L. Price, "Uncertainties Associated with Performance Assessment of High-Level Radioactive Waste Repositories," NUREG/CR-5211, SAND88-2703, U. S. Nuclear Regulatory Commission, 1990.
-
(1990)
Uncertainties Associated with Performance Assessment of High-Level Radioactive Waste Repositories
-
-
Davis, P.1
Bonano, E.J.2
Wahi, K.K.3
Price, L.L.4
-
130
-
-
85031609971
-
-
Personal Communications, Brookhaven National Laboratory
-
Personal Communications, Terry M. Sullivan, Brookhaven National Laboratory, 1999.
-
(1999)
-
-
Sullivan, T.M.1
|