Development of maintenance significance evaluation method considering effect of pipe failure. Part 1. Proposition of evaluation method for maintenance index and construction of fluid leakage evaluation facility
Creators
- 1. Central Research Institute of Electric Power Industry, Nuclear Technology Research Laboratory, Yokosuka, Kanagawa (Japan)
Description
Since several safety-related systems were added to the nuclear power plants (light-water reactors) through the process of the new regulatory requirements, the number of components to be inspected in service, which has been already large, will increase more than ever after the restart. Effective measure will be required to reasonably assign limited resource to maintenance activities. The authors have proposed the evaluation method for maintenance index to aim optimization considering influence of fluid leakage behavior with pipe failure, mainly targeting non safety-related piping and components. In this research, maintenance methods (time based maintenance, condition based maintenance, extraction of maintenance region utilizing the prediction code etc.) are to be selected based on maintenance significance which is evaluated with pipe failure probability and pipe failure impact to surrounding components and operators. To evaluate pipe failure impact, experimental facility which can investigate fluid leakage behavior with pipe failure has been constructed. Using this facility, we can conduct a mock test of flashing and steam flow leakage from various flaw geometries of pipe (crack, pinhole and guillotine break). (author)
Availability note (English)
Available from https://criepi.denken.or.jp/jp/kenkikaku/report/detail/L16001.htmlAdditional details
Additional titles
- Original title (Japanese)
- 配管破損時影響を考慮した保全重要度評価手法の開発 (その1).保全指標評価手順の提案と流体漏洩挙動計測設備の構築
Identifiers
Publishing Information
- Imprint Pagination
- 34 p.
- Report number
- CRIEPI--L16001
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 49083801
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; CRACKS; FAILURES; FLASHING; FLOW VISUALIZATION; GAS FLOW; HOT WATER; IN-SERVICE INSPECTION; LEAKS; NUCLEAR POWER PLANTS; PIPES; PROBABILITY; PWR TYPE REACTORS; REACTOR MAINTENANCE; STEAM
- Descriptors DEC
- ENRICHED URANIUM REACTORS; EVAPORATION; FLUID FLOW; HYDROGEN COMPOUNDS; INSPECTION; MAINTENANCE; NUCLEAR FACILITIES; OPERATION; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; POWER PLANTS; POWER REACTORS; REACTOR LIFE CYCLE; REACTOR OPERATION; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; TUBES; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 18 refs., 31 figs., 1 tab.