Published January 1988
| Version v1
Journal article
Utilization survey of PRAISE-B, reactor piping reliability assessment code, based on probabilistic fracture mechanics
Creators
- 1. Central Research Inst. of Electric Power Industry, Komae, Tokyo (Japan). Komae Research Lab.
Description
In the United States, in order to obtain better evaluation of the reliability of nuclear components, several codes, based on probabilistic fracture mechanics, have already been developed. One of these codes, PRAISE-B (Piping Reliability Assessment Including Seismic Event), has been surveyed for more efficient utilization, and the following conclusions have been obtained. (1) PRAISE-B requires only simple input, yet contains various functions for piping failure probability evaluation. (2) Tearing modulus instability as well as plastic collaps should be taken into consideration as failure criteria when the code is applied to LBB (leak-before-break) assessment. (author)
Additional details
Publishing Information
- Journal Title
- Denryoku Chuo Kenkyusho Hokoku
- Journal Issue
- no.T87012
- Series
- Denryoku Chuo Kenkyusho Hokoku.
- CODEN
- DCKHD
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 20034810
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- BWR TYPE REACTORS; CRACK PROPAGATION; EARTHQUAKES; FRACTURE MECHANICS; MONTE CARLO METHOD; NONDESTRUCTIVE TESTING; NUMERICAL SOLUTION; P CODES; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; RELIABILITY; STRESS CORROSION; STRESSES; TUBES
- Descriptors DEC
- CHEMICAL REACTIONS; COMPUTER CODES; COOLING SYSTEMS; CORROSION; ENRICHED URANIUM REACTORS; MATERIALS TESTING; MECHANICS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS