Role of recent research in improving check valve reliability at nuclear power plants
Creators
- 1. Kalsi Engineering, Inc., Sugar Land, TX (United States)
Description
Check valve failures in nuclear power plants have led to safety concerns as well as extensive damage and loss of plant availability in recent years. Swing check valve internals may experience premature deterioration if the disc is not firmly held open against its stop. At the present time no guidelines exist for the prediction of degradation trends and the determination of suitable inspection intervals. This research is aimed at developing a reliable quantitative wear and fatigue prediction model for swing check valves which can be used to improve the safety and reliability of their operation. Additionally, the predictive techniques can be used to augment check valve preventive maintenance programs by providing the plant engineer with quantitative and conservative estimates of damage potential for check valve internals
Additional details
Publishing Information
- Imprint Title
- Eighteenth water reactor safety information meeting. Volume 3, Pressure vessel integrity; Piping and NDE; Aging and components: Proceedings
- Imprint Pagination
- 574 p.
- Journal Page Range
- p. 485-538.
- Report number
- NUREG/CP--0114-Vol.3
Conference
- Title
- 18. water reactor safety information meeting.
- Dates
- 22-24 Oct 1990.
- Place
- Rockville, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24038758
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; AVAILABILITY; BWR TYPE REACTORS; FAILURES; FATIGUE; FLOW RATE; FLUID-STRUCTURE INTERACTIONS; IMPACT STRENGTH; INSPECTION; MATHEMATICAL MODELS; PWR TYPE REACTORS; REACTOR MAINTENANCE; REACTOR OPERATION; REACTOR SAFETY; RELIABILITY; RESEARCH PROGRAMS; TURBULENCE; US NRC; VALVES; WEAR
- Descriptors DEC
- CONTROL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; MAINTENANCE; MECHANICAL PROPERTIES; NATIONAL ORGANIZATIONS; OPERATION; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-9010185--Vol.3.