Radionuclide transport in the vicinity of the repository and associated complementary cumulative distribution functions in the 1996 performance assessment for the Waste Isolation Pilot Plant

Reliability Engineering and System Safety

Volumn 69, Issue 1, 2000, Pages 369-396

  Stockman, C T ^a   Garner, J W ^b   Helton, J C ^a,c   Johnson, J D ^d   Shinta, A ^e   Smith, L N ^f  

^a SANDIA NATIONAL LABORATORIES   (United States)

^b Piru Associates   (United States)

^c ARIZONA STATE UNIVERSITY   (United States)

^d GRAM Incorporated   (United States)

^e Applied Physics Inc   (United States)

^f Comforce ^*  (United States)

Author keywords

[No Author keywords available]

Indexed keywords

ENVIRONMENTAL PROTECTION; GEOLOGICAL REPOSITORIES; MATHEMATICAL MODELS; MONTE CARLO METHODS; PILOT PLANTS; RADIOISOTOPES; RANDOM PROCESSES; REGULATORY COMPLIANCE; RISK ASSESSMENT; SENSITIVITY ANALYSIS;

COMPLEMENTARY CUMULATIVE DISTRIBUTION FUNCTIONS (CCDF); EPISTEMIC UNCERTAINTY; HYPERCUBE SAMPLING; PERFORMANCE ASSESSMENT (PA); SUBJECTIVE UNCERTAINTY; TRANSURANIC WASTES;

RADIOACTIVE WASTE DISPOSAL;

EID: 0343889811     PISSN: 09518320     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0951-8320(00)00039-9     Document Type: Article

References (36)

1. US Department of Energy. Title 40 CFR Part 191 compliance certification application for the Waste Isolation Pilot Plant. DOE/CAO-1996-2184, Vols. I-XXI. US Department of Energy, Carlsbad Area Office, Carlsbad, NM, 1996.
2. Howard BA, Crawford MB, Galson DA, Marietta MG. Regulatory basis for the Waste Isolation Pilot Plant performance assessment. Reliability Engineering and System Safety 2000;69(1-3):109-27.
3. US Environmental Protection Agency. 40 CFR Part 191: Environmental standards for the management and disposal of spent nuclear fuel, high-level and transuranic radioactive wastes, final rule, Federal Register 1985;50(182):38 066-89.
4. US Environmental Protection Agency. 40 CFR Part 191: Environmental radiation protection standards for the management and disposal of spent nuclear fuel, high-level and transuranic radioactive wastes, final rule, Federal Register 1993;5(242):66 398-416.
5. US Environmental Protection Agency. 40 CFR Part 194: Criteria for the certification and re-certification of the Waste Isolation Pilot Plant's compliance with the 40 CFR Part 191 disposal regulations, final rule. Federal Register 1996;61(28):5224-45.
6. Berglund JW, Garner JW, Helton JC, Johnson JD, Smith LN. Direct releases to the surface and associated complementary cumulative distribution functions in the 1996 performance assessment for the Waste Isolation Pilot Plant: cuttings, cavings and spallings. Reliability Engineering and System Safety 2000;69(1-3):305-30.
7. Knowles MK, Hansen FD, Thompson TW, Gross MB, Schatz JF. Review and perspectives on spallings releases in the 1996 performance assessment for the Waste Isolation Pilot Plant. Reliability and System Safety 2000;69(1-3):331-41.
8. Stoelzel DM, O'Brien DG, Garner JW, Helton JC, Johnson JD, Smith LN. Direct releases to the surface and associated complementary cumulative distribution functions in the 1996 performance assessment for the Waste Isolation Pilot Plant: direct brine releases. Reliability Engineering and System Safety 2000;69(1-3):343-67.
9. Ramsey JL, Blaine R, Garner JW, Helton JC, Johnson JD, Smith LN, Wallace M. Radionuclide and colloid transport in the Culebra Dolomite and associated complementary cumulative distribution functions in the 1996 performance assessment for the Waste Isolation Pilot Plant. Reliability Engineering and System Safety 2000;69(1-3):397-420.
10. Helton JC, Anderson DR, Basabilvazo G, Jow H-N, Marietta MG. Conceptual structure of the 1996 performance assessment for the Waste Isolation Pilot Plant. Reliability Engineering and System Safety 2000;69(1-3):151-65.
11. Helton JC, Davis FJ, Johnson JD. Characterization of stochastic uncertainty in the 1996 performance assessment for the Waste Isolation Pilot Plant. Reliability Engineering and System Safety 2000;69(1-3):167-89.
12. Helton JC, Martell M-A, Tierney MS. Characterization of subjective uncertainty in the 1996 performance assessment for the Waste Isolation Pilot Plant. Reliability Engineering and System Safety 2000;69(1-3):191-204.
13. Vaughn P, Bean JE, Helton JC, Lord ME, MacKinnon RJ, Schreiber JD. Representation of two-phase flow in the vicinity of the repository in the 1996 performance assessment for the Waste Isolation Pilot Plant. Reliability Engineering and System Safety 2000;69(1-3):205-26.
14. Helton JC, Anderson DR, Basabilvazo G, Jow H-N, Marietta MG. Summary discussion of the 1996 performance assessment for the Waste Isolation Pilot Plant. Reliability Engineering and System Safety 2000;69(1-3):437-51.
15. McKay MD, Beckman RJ, Conover WJ. A comparison of three methods for selecting values of input variables in the analysis of output from a computer code. Technometrics 1979;21(2):239-45.
16. Helton JC. Uncertainty and sensitivity analysis techniques for use in performance assessment for radioactive waste disposal. Reliability Engineering and System Safety 1993;42(2-3):327-67.
17. Helton JC, Bean JE, Economy K, Garner JW, MacKinnon RJ, Miller J, Schreiber JD, Vaughn P. Uncertainty and sensitivity analysis for two-phase flow conditions in the vicinity of the repository in the 1996 performance assessment for the Waste Isolation Pilot Plant: undisturbed conditions. Reliability Engineering and System Safety 2000;69(1-3):227-61.
18. Helton JC, Bean JE, Economy K, Garner JW, MacKinnon RJ, Miller J, Schreiber JD, Vaughn P. Uncertainty and sensitivity analysis for two-phase flow in the vicinity of the repository in the 1996 performance assessment for the Waste Isolation Pilot Plant: disturbed conditions. Reliability Engineering and System Safety 2000;69(1-3):263-304.
19. Helton JC, Bean JE, Berglund JW, Davis FJ, Economy K, Garner JW, Johnson JD, MacKinnon RJ, Miller J, O'Brien DG, Ramsey JL, Schreiber JD, Shinta A, Smith LN, Stoelzel DM, Stockman C, Vaughn P. Uncertainty and sensitivity analysis results obtained in the 1996 performance assessment for the Waste Isolation Pilot Plant. SAND98-0365. Sandia National Laboratories, Albuquerque, NM, 1998.
20. Stockman C, Shinta A, Garner JW. Analysis package for the Salado transport calculations (Task 2) of the performance assessment analysis supporting the compliance certification application. Sandia WIPP Central Files WPO #40515. Sandia National Laboratories, Albuquerque, NM, 1996.
21. Siegel MD. Solubility parameters for actinide source term look-up tables. Records package. Sandia WIPP Central Files WPO #35835. Sandia National Laboratories, Albuquerque, NM, 1996.
22. US Department of Energy. Transuranic waste baseline inventory report (Revision 2). DOE/CAO-95-1121, Revision 2. US Department of Energy, Carlsbad Area Office, Carlsbad, NM, 1995.
23. Sanchez LC, Liscum-Powell J, Rath JS, Trellue HR. WIPP PA analysis report for EPAUNI: estimating probability distribution of EPA unit loading in the WIPP repository for performance assessment calculations, Version 1.01. Sandia WIPP Central Files WPO #43843. Sandia National Laboratories, Albuquerque, NM, 1997.
24. Sanchez LL, Drez PE, Rath JSC, Trellue HR. Radioactive and nonradioactive waste intended for disposal at the Waste Isolation Pilot Plant. Reliability Engineering and System Safety, 2000;69(1-3):99-107.
25. WIPP PA (Performance Assessment) Department, NUTS, version 2.02 user's manual, Sandia WIPP Central Files WPO #37927. Sandia National Laboratories, Albuquerque, NM, 1996.
26. Aziz K, Settari A. Petroleum reservoir simulation. London (New York): Applied Science Publishers (Elsevier), 1979.
27. Stockman CT, Moore RC. Use of dissolved and colloidal actinide parameters within the 1996 Waste Isolation Pilot Plant compliance certification application. SAND98-1062C, 1998.
28. WIPP PA (Performance Assessment) Department, PANEL, version 3.60, user's manual, Sandia WIPP Central Files WPO #37361. Sandia National Laboratories, Albuquerque, NM, 1996.
29. Bateman H. The solution of a system of differential equations occurring in the theory of radioactive transformations. Proceedings of the Cambridge Philosophical Society 1910;15(5):423-7.
30. Iman RL, Davenport JM, Frost EL, Shortencarier MJ. Stepwise regression with PRESS and rank regression (program and user's guide). SAND79-1472. Sandia National Laboratories, Albuquerque, NM, 1980.
31. WIPP PA (Performance Assessment) Department. STEPWISE, version 2.20, user's manual, document version 1. Sandia WIPP Central Files WPO #27768. Sandia National Laboratories, Albuquerque, NM, 1995.
32. Iman RL, Conover WJ. The use of the rank transform in regression. Technometrics 1979;21(4):499-509.
33. Papenguth HW. Development of parameter values describing colloidal actinide retardation in the Culebra Dolomite, document in records package: colloidal actinide retardation parameters. Sandia WIPP Central Files WPO #38173. Sandia National Laboratories, Albuquerque, NM, 1996.
34. Helton JC, Garner JW, Marietta MG, Rechard RP, Rudeen DK, Swift PN. Uncertainty and sensitivity analysis results obtained in a preliminary performance assessment for the Waste Isolation Pilot Plant. Nuclear Science and Engineering 1993;114(4):286-331.
35. Helton JC, Anderson DR, Baker BL, Bean JE, Berglund JW, Beyeler W, Garner JW, Iuzzolino HJ, Marietta MG, Rechard RP, Roache PJ, Rudeen DK, Schreiber JD, Swift PN, Tierney MS, Vaughn P. Effect of alternative conceptual models in a preliminary performance assessment for the Waste Isolation Pilot Plant. Nuclear Engineering and Design 1995;154(3):251-344.
36. Helton JC, Anderson DR, Baker BL, Bean JE, Berglund JW, Beyeler W, Economy K, Garner JW, Hora SC, Iuzzolino HJ, Knupp P, Marietta MG, Rath J, Rechard RP, Roache PJ, Rudeen DK, Salari K, Schreiber JD, Swift PN, Tierney MS, Vaughn P. Uncertainty and sensitivity analysis results obtained in the 1992 performance assessment for the Waste Isolation Pilot Plant. Reliability Engineering and System Safety 1996;51(1):53-100.