Estimates of rupture probabilities for nuclear power plant components; Expert judgment elicitation
Journal Article
·
· Nuclear Technology; (United States)
OSTI ID:5417004
- Pacific Northwest Lab., Richland, WA (United States)
This paper reports that as part of the nondestructive evaluation reliability program sponsored by the U.S. Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory (PNL) developed a risk-based method for establishing inspection priorities for systems and components at nuclear power plants. In this method, the results of probabilistic risk assessment (PRA) are used to estimate the safety consequences of component failures. The method also requires estimates of the probabilities of structural failures. Since sufficient operating experience data and detailed fracture mechanics analyses are not available, an expert judgment elicitation is conducted to estimate component rupture probabilities. (An expert judgment process is generally adapted from the NRC severe accident risk program).
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 5417004
- Journal Information:
- Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 96:3; ISSN 0029-5450; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
Similar Records
Estimates of component rupture probabilities for pressure boundary systems in LWRs
Simplified Expert Elicitation Procedure for Risk Assessment of Operating Events
Evaluation of the use of expert judgment to estimate human error probabilities
Conference
·
Mon Dec 31 23:00:00 EST 1990
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:5777306
Simplified Expert Elicitation Procedure for Risk Assessment of Operating Events
Technical Report
·
Wed Jun 01 00:00:00 EDT 2005
·
OSTI ID:911228
Evaluation of the use of expert judgment to estimate human error probabilities
Conference
·
Sat Dec 31 23:00:00 EST 1983
·
OSTI ID:6330287
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
BATTELLE PACIFIC NORTHWEST LABORATORIES
CHEMICAL ANALYSIS
DATA
ENRICHED URANIUM REACTORS
FAILURES
FRACTURE MECHANICS
INFORMATION
MECHANICS
NATIONAL ORGANIZATIONS
NONDESTRUCTIVE ANALYSIS
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RELIABILITY
RISK ASSESSMENT
RUPTURES
SAFETY
SURRY-2 REACTOR
THERMAL REACTORS
US DOE
US ERDA
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
BATTELLE PACIFIC NORTHWEST LABORATORIES
CHEMICAL ANALYSIS
DATA
ENRICHED URANIUM REACTORS
FAILURES
FRACTURE MECHANICS
INFORMATION
MECHANICS
NATIONAL ORGANIZATIONS
NONDESTRUCTIVE ANALYSIS
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RELIABILITY
RISK ASSESSMENT
RUPTURES
SAFETY
SURRY-2 REACTOR
THERMAL REACTORS
US DOE
US ERDA
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS