Published August 2017
| Version v1
Journal article
PSA methodology study for RPV pressurized thermal shock
Creators
- 1. Shanghai Nuclear Engineering Research & Design Institute, Shanghai (China)
Description
During transient, the inner surface of pressurized reactor pressure vessel (RPV) is cooled quickly, which is termed as pressurized thermal shock (PTS). So, a flaw may be caused and propagate through the RPV wall, that makes the RPV failure. Probabilistic safety assessment (PSA) is used to analysis the frequency of RPV flaw due to PTS. PSA model finds out the PTS event sequences, combining with the thermal hydraulic analysis, which supports the probabilistic fracture mechanics analysis for PTS. (authors)
Additional details
Publishing Information
- Journal Title
- Chinese Journal of Nuclear Science and Engineering
- Journal Volume
- 37
- Journal Issue
- 4
- Journal Page Range
- p. 521-524
- ISSN
- 0258-0918
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 52062349
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DEFECTS; FAILURES; FRACTURE MECHANICS; PRESSURE VESSELS; PROBABILISTIC ESTIMATION; RISK ASSESSMENT; SURFACES; THERMAL HYDRAULICS; THERMAL SHOCK; TRANSIENTS; WALLS
- Descriptors DEC
- CALCULATION METHODS; CONTAINERS; FLUID MECHANICS; HYDRAULICS; MECHANICS
Optional Information
- Notes
- 2 figs., 2 refs.