Published August 1986
| Version v1
Journal article
J and J' integral evaluation of a crack in a reactor pressure vessel under pressurized thermal shock
Creators
- 1. Science Univ. of Tokyo, Noda, Chiba (Japan). Faculty of Science and Technology
Description
J and J' integrals are evaluated for an assumed crack in a rector pressure vessel under pressurized thermal shock (PTS) conditions. First, two dimensional analyses are carried out assuming the cladding on the inner surface of the vessel wall. Several kinds of PTS conditions are treated, and it is shown that the RFT condition gives the most severe results. J values are compared with JIc and JIa and the possibilies of the crack growth in the vessel wall are discussed. Second, three dimensional analyses are conducted and the results are compared with those of two dimensional analyses. (author)
Additional details
Publishing Information
- Journal Title
- Nippon Kikai Gakkai Ronbunshu, A Hen
- Journal Volume
- 52
- Journal Issue
- 480
- Series
- Nippon Kikai Gakkai Ronbunshu, A Hen.
- Journal Page Range
- 1913-1920
- ISSN
- 0387-5008
- CODEN
- NKGAD
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 18070130
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CRACKS; ELASTICITY; FRACTURES; INTEGRALS; PRESSURE VESSELS; PWR TYPE REACTORS; STAINLESS STEELS; STRESSES; SURFACES; TEMPERATURE DISTRIBUTION; THERMAL SHOCK; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CONTAINERS; ENRICHED URANIUM REACTORS; FAILURES; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; POWER REACTORS; REACTORS; STEELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS