Estimates of component rupture probabilities for pressure boundary systems in LWRs
Creators
- 1. Battelle - Pacific Northwest Lab., Richland, WA (United States)
Description
The goals of a multiyear program entitled Nondestructive Evaluation Reliability for Inservice Inspection of Light Water Reactors, which is being conducted at Pacific Northwest Laboratory (PNL) for the US Nuclear Regulatory Commission, are to determine the reliability of current in-service inspections of pressure boundary systems and components and to develop recommendations that can ensure a suitably high inspection reliability. The long-term objective is to develop recommendations for improved inspection plans that address inspection samples, frequencies, and methods. In meeting the program objectives, PNL has developed risk-based methods as a guide for establishing inspection priorities. In PNL's pilot application of risk-based methods, the limitations of historical failure rate data became evident, and it was not possible to exercise probabilistic fracture mechanics models. Therefore, expert judgment was selected for estimating failure probabilities. The goal was to obtain numerical estimates for probabilities of catastrophic failures (i.e., ruptures) in pressure boundary systems and components of pressurized water reactors. The representative plant selected for the study was the Surry nuclear power station unit 1 (Surry-1). This paper summarizes the process and the results of the expert judgment elicitation for selected systems at Surry-1
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 63
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 281-283
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- Annual meeting of the American Nuclear Society (ANS).
- Dates
- 2-6 Jun 1991.
- Place
- Orlando, FL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23036667
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BATTELLE PACIFIC NORTHWEST LAB; BWR TYPE REACTORS; FAILURES; FRACTURE MECHANICS; HISTORICAL ASPECTS; IN-SERVICE INSPECTION; LOSS OF COOLANT; MANAGEMENT; NONDESTRUCTIVE TESTING; PRIMARY COOLANT CIRCUITS; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR SAFETY; RELIABILITY; RUPTURES; SURRY-1 REACTOR; TRAINING; US NRC
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; EDUCATION; ENRICHED URANIUM REACTORS; INSPECTION; MATERIALS TESTING; MECHANICS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; TESTING; THERMAL REACTORS; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-910603--.