Published 1996 | Version v1
Report Open

Reliability estimation for check valves and other components

Description

For years the nuclear industry has depended upon component operational reliability information compiled from reliability handbooks and other generic sources as well as private databases generated by recognized experts both within and outside the nuclear industry. Regrettably, these technical bases lacked the benefit of large-scale operational data and comprehensive data verification, and did not take into account the parameters and combinations of parameters that affect the determination of failure rates. This paper briefly examines the historic use of generic component reliability data, its sources, and its limitations. The concept of using a single failure rate for a particular component type is also examined. Particular emphasis is placed on check valves due to the information available on those components. The Appendix presents some of the results of the extensive analyses done by Oak Ridge National Laboratory (ORNL) on check valve performance

Availability note (English)

MF available from INIS under the Report Number; Also available from OSTI as DE96009877; NTIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
8 p.
Report number
CONF-960706--5

Conference

Title
American Society of Mechanical Engineers (ASME) pressure vessels and piping conference.
Dates
21-26 Jul 1996.
Place
Montreal (Canada).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
27066030
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FAILURES; HISTORICAL ASPECTS; INFORMATION SYSTEMS; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; REACTOR COMPONENTS; RELIABILITY; VALVES
Descriptors DEC
CONTROL EQUIPMENT; EQUIPMENT; FLOW REGULATORS; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS

Optional Information