Risk Impacts of Pressurizer Safety Valve Reseat Failure
Creators
- 1. Korea Electric Power Research Institute, Taejon (Korea, Republic of)
Description
In an effort to develop probabilistic safety assessments (PSAs) that are as realistic as possible, component failure rates are traditionally based on a combination of experience, component testing, and expert judgment. During various accident sequences modeled in the PSA, the pressurizer safety valves (PSVs) of a pressurized water reactor (PWR) may cycle numerous times. The PSVs will initially relieve steam. In some longer duration accident sequences, the steam relief will eventually become liquid relief. With each cycle of the PSV, there is a probability that the safety valve will fail to reseat. The PSV failure-to-reseat results in the need for additional mitigative systems to prevent core damage. This paper describes a quantitative assessment to identify risk impacts of the failure probability due to the repeated cycling operation of PSVs (pressurizer safety valves) under severe accidents
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS autumn meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2005 autumn meeting of the KNS
- Dates
- 27-28 Oct 2005
- Place
- Busan (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 37072206
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- FAILURES; HAZARDS; PRESSURIZERS; PROBABILITY; PWR TYPE REACTORS; RELIEF VALVES; SAFETY ANALYSIS
- Descriptors DEC
- CONTROL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; POWER REACTORS; REACTORS; THERMAL REACTORS; VALVES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 3 refs, 3 figs