検索対象:     
報告書番号:
※ 半角英数字
 年 ~ 
 年

確率論的破壊力学解析手法を用いた加圧熱衝撃時における原子炉圧力容器の耐圧機能喪失頻度の試評価

Evaluation of through-wall cracking frequency of reactor pressure vessel under pressurized thermal shock events using probabilistic fracture mechanics analysis method

西川 弘之*; 眞崎 浩一*; 小坂部 和也*; 勝山 仁哉  ; 鬼沢 邦雄 

Nishikawa, Hiroyuki*; Masaki, Koichi*; Osakabe, Kazuya*; Katsuyama, Jinya; Onizawa, Kunio

国内の原子炉圧力容器(RPV)の加圧熱衝撃(PTS)事象時の健全性評価では、決定論的手法による破壊力学評価がなされているのに対し、米国では確率論的手法に基づく評価が実施されている。原子力規制庁からの受託事業「高経年化技術評価高度化事業(平成23年度$$sim$$平成27年度(予定)」の平成24年度における成果として、米国における評価方法を参考に、RPVの照射脆化が大きい場合の耐圧機能喪失頻度(TWCF)を確率論的破壊力学解析コードPASCAL3により評価した結果について報告する。TWCFを用いることで、き裂の位置や方向、過渡事象などの条件がRPVの健全性に及ぼす影響を定量的に比較できることを示した。

To assure the structural integrity of a reactor pressure vessel (RPV) is one of the most critical issues to maintain the safe long-term operation of a nuclear power plant. In Japan, the assessment methods for RPV integrity using deterministic fracture mechanics, provided in the codes and standards, have been endorsed by the regulatory body. Meanwhile, a regulation on the fracture toughness requirements against PTS events with a probabilistic approach has been established in the U.S. In this paper, referring to the approach in the U.S., the through-wall cracking frequency (TWCF) for aging RPV in Japan against PTS events was calculated using a probabilistic fracture mechanics analysis code PASCAL3. As the results, we clarified that existing methodology on structural integrity assessment of RPV considering postulated axial flaw has a certain amount of conservativeness, and the value of TWCF is useful to assess impacts on structural integrity of RPV quantitatively.

Access

:

- Accesses

InCites™

:

Altmetrics

:

[CLARIVATE ANALYTICS], [WEB OF SCIENCE], [HIGHLY CITED PAPER & CUP LOGO] and [HOT PAPER & FIRE LOGO] are trademarks of Clarivate Analytics, and/or its affiliated company or companies, and used herein by permission and/or license.