Published March 1994
| Version v1
Journal article
An analytical method for leak before break assessment based upon stochastic fracture mechanics
- 1. Kyoto Univ. (Japan). Dept. of Applied Mathematics and Physics
- 2. Fukui Prefectural Univ. (Japan). Center for Information Science
Description
An analytical method is proposed for probabilistic assessment of LBB in piping systems based upon stochastic fracture mechanics. Basically, we follow the assumptions such that: (i) The surface crack propagation can be decomposed into surface and depth directions, (ii) the well-known Paris' law is applicable to each direction, (iii) the Newman-Raju's expression is applicable for the stress intensity factor of the surface crack. First, by taking into account the randomness of material's property and loading, a probability density function of random surface crack propagation is derived with the aid of a Markov approximation method. Next, discussion is made on how we apply the result to the probabilitic LBB assessment. (orig.)
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 147
- Journal Issue
- 2
- Journal Page Range
- p. 171-181.
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 25052617
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; CRACK PROPAGATION; CRACKS; FRACTURE MECHANICS; FRACTURES; LEAKS; LOSS OF COOLANT; MARKOV PROCESS; PIPES; PROBABILISTIC ESTIMATION; PROBABILITY; PWR TYPE REACTORS; STOCHASTIC PROCESSES; STRESS INTENSITY FACTORS
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; FAILURES; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS