Published 1988
| Version v1
Book
Dominant factors in evaluation of pressure vessel integrity during Pts events
Creators
Description
A code system PLES/PTS has been developed to evaluate the integrity of pressure vessel during plant thermal-hydraulic transients related to pressurized thermal shock. The system consists of codes for the analyses of system thermal-hydraulics, thermal-mixing, stress distribution within vessel walls, and fracture mechanics (FM) parameters. Using this code system, evaluations have been performed for Japanese typical 2-, 3- and 4-loop plants and the dependence on the number of loops has been discussed. In order to well understand the results, sensitivity calculations on the thermal-hydraulic conditions and the material factors which influence the FM parameters have been carried out
Additional details
Publishing Information
- Publisher
- Societe Francaise d'Energie Nucleaire.
- Imprint Place
- Paris (France)
- Imprint Title
- Proceedings of the International ENS/ANS Conference on thermal reactor safety. Volume 2
- Imprint Pagination
- 460 p.
- Journal Page Range
- p. 841-850.
Conference
- Title
- International ENS/ANS Conference on thermal reactor safety.
- Dates
- 2-7 Oct 1988.
- Place
- Avignon (France).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 21020339
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- JAERI; P CODES; PWR TYPE REACTORS; REACTOR ACCIDENTS; SENSITIVITY ANALYSIS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; JAPANESE ORGANIZATIONS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS