Published October 2013
| Version v1
Journal article
Analysis of fast fracture of core region of RPV
- 1. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu (China)
Description
The core region of reactor pressure vessel is the main part irradiated by the core, since irradiation raises the nil ductility transition temperature. This increases the sensibility to fast fracture. To prevent the vessel fast fracture of vessel, the fast fracture mechanics analysis is necessary in the design of reactor vessel. In the paper, fast fracture mechanics analysis was performed using the first method and the second method for RPV according to RCC-M. The analysis results met the allowable limits. (authors)
Additional details
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 34
- Journal Issue
- 5
- Journal Page Range
- p. 30-32
- ISSN
- 0258-0926
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 47112357
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DESIGN; DUCTILITY; FRACTURE MECHANICS; FRANCE; IRRADIATION; PRESSURE VESSELS; PWR TYPE REACTORS; STANDARDS; TRANSITION TEMPERATURE
- Descriptors DEC
- CONTAINERS; DEVELOPED COUNTRIES; ENRICHED URANIUM REACTORS; EUROPE; MECHANICAL PROPERTIES; MECHANICS; PHYSICAL PROPERTIES; POWER REACTORS; REACTORS; TENSILE PROPERTIES; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; WATER COOLED REACTORS; WATER MODERATED REACTORS; WESTERN EUROPE
Optional Information
- Notes
- 2 figs., 1 tab., 1 refs.