Study on risk-informed in-service inspection for BWR piping
Creators
- 1. Japan Nuclear Energy Safety Organization, Tokyo (Japan)
- 2. CSA of Japan Co., Ltd., Tokyo (Japan)
Description
Risk-informed in-service inspection for piping was studied for a BWR plant. Piping segment rupture probabilities were determined by Bayesian transform from piping failure events in the database of the OECD-NEA Piping Failure Data Exchange project. Based on the methodology of the Westinghouse Owners Group, core damage frequency induced by each segment rupture was determined by the use of a surrogate component in the PSA model. Nondestructive examinations were added to leak examinations for segments of the resultant high risk significance. The changes from current examinations gave around 29% reduction of segments subject to both leak and nondestructive examinations within the total segments. Deterministic insights and engineering judgements on top of risk significance should be applied to obtain the final decision of inspection methods. An extent-of-examination was studied by the adoption of the Perdue-Abramson model in the Westinghouse Owners Group methodology. The necessary leak frequency of a crack in a segment was calculated by the probabilistic fracture mechanics code PRAISE. Two segments of high risk significance showed lower or slightly higher extents-of-examination, respectively, than the current extent-of-examination. To contribute to the enhancement of the scientific rationality of piping inspections, technical knowledge was accumulated. (author)
Availability note (English)
Available from http://dx.doi.org/10.3327/jnst.46.846Additional details
Identifiers
- DOI
- 10.3327/jnst.46.846;
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo)
- Journal Volume
- 46
- Journal Issue
- 8
- Journal Page Range
- p. 846-873
- ISSN
- 0022-3131
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 41004542
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; DAMAGE; HAZARDS; INFORMATION; IN-SERVICE INSPECTION; LEAKS; NONDESTRUCTIVE TESTING; PIPES; PROBABILISTIC ESTIMATION; REACTOR CORES; RISK ASSESSMENT; RUPTURES
- Descriptors DEC
- CALCULATION METHODS; ENRICHED URANIUM REACTORS; FAILURES; INSPECTION; MATERIALS TESTING; POWER REACTORS; REACTOR COMPONENTS; REACTORS; TESTING; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 38 refs., 5 figs., 14 tabs.