Improvement of probabilistic fracture mechanics evaluation code PEDESTRIAN for piping. Implementation of evaluation methods for crack propagation
Creators
- 1. Central Research Institute of Electric Power Industry, Energy Transformation Research Laboratory, Materials Science Division, Yokosuka, Kanagawa (Japan)
Description
Probabilistic fracture mechanism (PFM) is recently featured as a promising technology for quantitative and reasonable structural integrity evaluation method for nuclear components. United States of America is leading the scene from code development to its implementation into regulatory requirement. U. S. Nuclear Regulatory Commission and EPRI are developing a PFM code named 'xLPR' for evaluation of leak-before-break of primary water stress corrosion cracking. The xLPR has recently been released for institutions outside the US, but its computation speed is slow. A PROLOCA code consists almost the same modules as the xLPR and calculates faster than the xLPR. These codes were developed in accordance with U. S. regulatory requirement. CRIEPI has developed a PEDESTRIAN code for structural integrity assessment of piping in Japanese plants. In order to apply PFM to structural integrity assessment, an analysis code is necessary to establish Japanese evaluation system with reference to leading U. S. perception. In this study, we investigated the evaluation methods on the xLPR, and implemented the methods, which are considered to be important, on the PEDESTRIAN. The deterministic and probabilistic analyses were conducted by using the updated PEDESTRIAN, and then these results were compared with those obtained by PROLOCA. Consequently, the deterministic and probabilistic results were in good agreement with each other. (author)
Availability note (English)
Available from https://criepi.denken.or.jp/hokokusho/pb/reportDetail?reportNoUkCode=EX22006Additional details
Additional titles
- Original title (Japanese)
- 配管用の確率論的破壊力学解析コードPEDESTRIANの整備.亀裂進展に関連した評価手法の実装
Publishing Information
- Imprint Pagination
- 22 p.
- Report number
- CRIEPI--EX22006
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 55018675
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- CRACK PROPAGATION; CRACKS; FRACTURE MECHANICS; LEAKS; NUCLEAR POWER PLANTS; P CODES; PIPES; PROBABILISTIC ESTIMATION; REACTOR COOLING SYSTEMS; RESIDUAL STRESSES; RUPTURES; STRESS CORROSION; STRESS INTENSITY FACTORS; WELDING
- Descriptors DEC
- CALCULATION METHODS; CHEMICAL REACTIONS; COMPUTER CODES; COOLING SYSTEMS; CORROSION; ENERGY SYSTEMS; FABRICATION; FAILURES; JOINING; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; STRESSES; THERMAL POWER PLANTS; TUBES
Optional Information
- Notes
- 38 refs., 5 figs., 2 tabs.