Recent Japanese research activities on probabilistic fracture mechanics for pressure vessel and piping of nuclear power plant |
| |
Authors: | Y. Kanto K. Onizawa H. Machida Y. Isobe S. Yoshimura |
| |
Affiliation: | 1. Department of Mechanical Engineering, Ibaraki University, Japan;2. Nuclear Safety Research Center, Japan Atomic Energy Agency, Japan;3. TEPCO Systems Corporation, Japan;4. Nuclear Fuel Industries Ltd., Japan;5. The University of Tokyo, Japan |
| |
Abstract: | This paper describes a review of recent Japanese activities on probabilistic fracture mechanics (PFM) analyses. Japan Atomic Energy Agency (JAEA: previously JAERI) had sponsored research committees on PFM organized by Japan Society of Mechanical Engineers (JSME) and Japan Welding Engineering Society (JWES) for more than a decade. This work still continues with the same members in JWES. The purpose of the continuous activity is to provide probabilistic approaches in several fields of integrity problems of nuclear power plant. This paper shows some of the newest results of the JWES research committee. First topic is evaluation of the new JSME code case with rules of Fitness-For-Service from the view of PFM, including reactor pressure vessel subject to pressurized thermal shock loading, piping with a crack of the allowable size and effect of sizing accuracy for piping integrity. The next one is development of new PFM techniques including reliability assessment of piping with domestic (Japanese) SCC data and maintenance optimization of LWRs based on risk and economic models. The last topic is the international round robin program just starting from 2008. |
| |
Keywords: | |
本文献已被 ScienceDirect 等数据库收录! |
|