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Benchmark analyses using probabilistic fracture mechanics analysis codes for reactor pressure vessels

原子炉圧力容器を対象とする確率論的破壊力学解析コードを用いたベンチマーク解析

荒井 健作*; 勝山 仁哉  ; Li, Y. 

Arai, Kensaku*; Katsuyama, Jinya; Li, Y.

原子力機構が開発した確率論的破壊力学(PFM)解析コードPASCAL及び米国のPFM解析コードFAVORを用いて、米国3ループ加圧水型原子炉の原子炉圧力容器を対象としたベンチマーク解析を実施した。応力拡大係数の式等の解析条件を一致させた結果、両コードの解析結果は良好に一致した。

Probabilistic fracture mechanics (PFM) analysis code PASCAL has been developed to assess structural integrity of aged reactor pressure vessels (RPVs) of light water nuclear power plants by Japan Atomic Energy Agency (JAEA). PASCAL is able to obtain failure frequency such as through-wall cracking frequency (TWCF) of RPVs under several transients including pressurized thermal shock (PTS) event. On the other hand, FAVOR was developed to perform almost the same analysis by Oak Ridge National Laboratory (ORNL) under United States Nuclear Regulatory Commission (USNRC) funding and has been utilized in the US nuclear regulation. To improve the reliability of PFM analysis results of PASCAL, benchmark analyses between PASCAL and FAVOR were performed. This paper provides results of the benchmark analyses using analysis conditions and parameters of the US 3-loop pressurized water reactor (PWR) nuclear power plant. Furthermore, sensitivity analyses relating to differences of analysis models (ex. Embrittlement correlation model) between Japan and the US were also conducted.

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