Published August 2017 | Version v1
Journal article

PSA methodology study for RPV pressurized thermal shock

  • 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

Optional Information

Notes
2 figs., 2 refs.