Published February 2012
| Version v1
Journal article
Pressurized thermal shock analysis for reactor pressure vessels
Creators
- 1. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu (China)
Description
According to RCC-M rule and NRC 10CFR50.61, the PTS analysis was performed for the reactor pressure vessel beltline with assumed defect. The end of-life reference temperature TR of nuclear power plant was calculated and assessed with PTS screening criteria. The stress intensity factors were calculated under PTS transients and assessed with RCC-M Rule. (authors)
Additional details
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 33
- Journal Issue
- 1
- Journal Page Range
- p. 1-3, 13
- ISSN
- 0258-0926
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 45102738
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- DEFECTS; NUCLEAR POWER PLANTS; PRESSURE DEPENDENCE; PRESSURE VESSELS; STRESS INTENSITY FACTORS; TEMPERATURE DEPENDENCE; THERMAL SHOCK; THERMAL STRESSES; TRANSIENTS
- Descriptors DEC
- CONTAINERS; NUCLEAR FACILITIES; POWER PLANTS; STRESSES; THERMAL POWER PLANTS
Optional Information
- Notes
- 7 figs., 3 refs.