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

Journal Article · Mon May 22 00:00:00 EDT 2000 · Reliability Engineering and System Safety (Special Journal Issue)

DOI:https://doi.org/10.1016/S0951-8320(00)00039-9· OSTI ID:755478

STOCKMAN, CHRISTINE T ^[1]; GARNER, J W; HELTON, JON CRAIG; JOHNSON, JAY DEAN; SHINTA, A; SMITH, L N

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1. Sandia National Laboratories

The following topics related to radionuclide transport in the vicinity of the repository in the 1996 performance assessment for the Waste Isolation Pilot Plant are presented (1) mathematical description of models, (2) uncertainty and sensitivity analysis results arising from subjective (i.e., epistemic) uncertainty for individual releases, (3) construction of complementary cumulative distribution functions (CCDFs) arising from stochastic (i.e., aleatory) uncertainty, and (4) uncertainty and sensitivity analysis results for CCDFs. The presented results indicate that no releases to the accessible environment take place due to radionuclide movement through the anhydrite marker beds, through the Dewey Lake Red Beds or directly to the surface, and also that the releases to the Culebra Dolomite are small. Even when the effects of uncertain analysis inputs are taken into account, the CCDFs for release to the Culebra Dolomite fall to the left of the boundary line specified in the US Environmental Protection Agency's standard for the geologic disposal of radioactive waste (40 CFR 191, 40 CFR 194).

• Research Organization: Sandia National Labs., Albuquerque, NM (US); Sandia National Labs., Livermore, CA (US)
• Sponsoring Organization: US Department of Energy (US)
• DOE Contract Number: AC04-94AL85000
• OSTI ID: 755478
• Report Number(s): SAND99-1887J
• Journal Information: Reliability Engineering and System Safety (Special Journal Issue), Journal Name: Reliability Engineering and System Safety (Special Journal Issue)
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
40 CFR 191
40 CFR 194
ALEATORY UNCERTAINTY
COMPLIANCE CERTIFICATION APPLICATION
DATA COVARIANCES
DISTRIBUTION FUNCTIONS
EPISTEMIC UNCERTAINTY
LATIN HYPERCUBE SAMPLING
MATHEMATICAL MODELS
MONTE CARLO
PERFORMANCE
PERFORMANCE ASSESSMENT
RADIOACTIVE WASTE
RADIONUCLIDE MIGRATION
RADIONUCLIDE TRANSPORT
RISK
RISK ASSESSMENT
SENSITIVITY ANALYSIS
STOCHASTIC UNCERTAINTY
SUBJECTIVE UNCERTAINTY
TRANSURANIC WASTE
WASTE ISOLATION PILOT PLANT
WIPP