Published 1978 | Version v1
Book Metadata-only

Common mode analysis of valve leakages

Creators

  • 1. Nuclear Regulatory Commission, Washington, DC

Description

A Marshall-Olkin based approach is applied to estimate common mode probabilities of valve leakages. The application utilizes recorded failure data to estimate the common mode probabilities and thus serves as an example of the utilization of current data sources in identifying and quantifying common mode failure probabilities

Additional details

Publishing Information

Publisher
American Nuclear Society, Inc.
Imprint Place
La Grange Park, IL
Imprint Title
Probabilistic analysis of nuclear reactor safety
Journal Page Range
p. X.5.1-X.5.8.

Conference

Title
Probabilistic analysis of nuclear reactor safety.
Dates
8 - 10 May 1978.
Place
Los Angeles, CA, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
10487508
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FAILURES; LEAKS; NUCLEAR POWER PLANTS; PEACH BOTTOM-2 REACTOR; REACTOR COOLING SYSTEMS; STATISTICS; VALVES
Descriptors DEC
BWR TYPE REACTORS; CONTROL EQUIPMENT; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; FLOW REGULATORS; MATHEMATICS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL POWER PLANTS; WATER COOLED REACTORS; WATER MODERATED REACTORS