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

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

OSTI ID:755476

HELTON, JON CRAIG ^[1]; BEAN, J E; ECONOMY, K; GARNER, J W; MACKINNON, ROBERT J; MILLER, JOEL D; SCHREIBER, J D; VAUGHN, PALMER

---

1. Sandia National Laboratories

Uncertainty and sensitivity analysis results obtained in the 1996 performance assessment (PA) for the Waste Isolation Pilot Plant (WIPP) are presented for two-phase flow in the vicinity of the repository under disturbed conditions resulting from drilling intrusions. Techniques based on Latin hypercube sampling, examination of scatterplots, stepwise regression analysis, partial correlation analysis and rank transformations are used to investigate brine inflow, gas generation repository pressure, brine saturation and brine and gas outflow. Of the variables under study, repository pressure and brine flow from the repository to the Culebra Dolomite are potentially the most important in PA for the WIPP. Subsequent to a drilling intrusion repository pressure was dominated by borehole permeability and generally below the level (i.e., 8 MPa) that could potentially produce spallings and direct brine releases. Brine flow from the repository to the Culebra Dolomite tended to be small or nonexistent with its occurrence and size also dominated by borehole permeability.

• 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: 755476
• Report Number(s): SAND99-1886J
• 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
BRAGFLO
BRINES
CALCULATION METHODS
COMPLIANCE CERTIFICATION APPLICATION
DATA COVARIANCES
DISTURBED CONDITIONS
EPISTEMIC UNCERTAINTY
GASES
LATIN HYPERCUBE SAMPLING
PERFORMANCE
PERFORMANCE ASSESSMENT
PERMEABILITY
PRESSURE DEPENDENCE
RADIOACTIVE WASTE
SENSITIVITY ANALYSIS
SUBJECTIVE UNCERTAINTY
TRANSURANIC WASTE
TWO-PHASE FLOW
UNCERTAINTY ANALYSIS
WASTE ISOLATION PILOT PLANT
WATER INFLUX
WELL DRILLING
WIPP