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: Undisturbed conditions

Journal Article · Fri May 19 00:00:00 EDT 2000 · Reliability Engineering and System Safety (Special Journal Issue)

OSTI ID:755475

HELTON, JON CRAIG; BEAN, J E; ECONOMY, K; GARNER, J W; MACKINNON, ROBERT J; MILLER, JOEL D; SCHREIBER, JAMES D; VAUGHN, PALMER

Uncertainty and sensitivity analysis results obtained in the 1996 performance assessment for the Waste Isolation Pilot Plant are presented for two-phase flow the vicinity of the repository under undisturbed conditions. Techniques based on Latin hypercube sampling, examination of scatterplots, stepwise regression analysis, partial correlation analysis and rank transformation are used to investigate brine inflow, gas generation repository pressure, brine saturation and brine and gas outflow. Of the variables under study, repository pressure is potentially the most important due to its influence on spallings and direct brine releases, with the uncertainty in its value being dominated by the extent to which the microbial degradation of cellulose takes place, the rate at which the corrosion of steel takes place, and the amount of brine that drains from the surrounding disturbed rock zone into the repository.

• Research Organization: Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sandia National Lab. (SNL-CA), Livermore, CA (United States)
• Sponsoring Organization: US Department of Energy (US)
• DOE Contract Number: AC04-94AL85000
• OSTI ID: 755475
• Report Number(s): SAND99-1885J; TRN: US0003608
• Journal Information: Reliability Engineering and System Safety (Special Journal Issue), Other Information: Submitted to Reliability Engineering and System Safety (Special Journal Issue); PBD: 19 May 2000
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
WIPP
PERFORMANCE
SENSITIVITY ANALYSIS
DATA COVARIANCES
TWO-PHASE FLOW
BRINES
GASES
CALCULATION METHODS
WATER INFLUX
RADIONUCLIDE MIGRATION
PRESSURE DEPENDENCE
BIODEGRADATION
CELLULOSE
STEELS
CORROSION
BRAGFLO
COMPLIANCE CERTIFICATION APPLICATION
EPISTEMIC UNCERTAINTY
LATIN HYPERCUBE SAMPLING
PERFORMANCE ASSESSMENT
RADIOACTIVE WASTE
SUBJECTIVE UNCERTAINTYH
TRANSURANIC WASTE
UNCERTAINTY ANALYSIS
UNDISTURBED CONDITIONS
WASTE ISOLATION PLANT PLANT