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Kai LU*, Jinya KATSUYAMA*, Yinsheng LI*, Yuhei MIYAMOTO**, Takatoshi HIROTA***, Yu ITABASHI****, Masaki NAGAI†, Masahide SUZUKI†† and Yasuhiro KANTO††† * Japan Atomic Energy Agency (JAEA) Shirakata 2-4, Tokai-mura, Naka-gun, Ibaraki 319-1195, Japan E-mail: lu.kai@jaea.go.jp ** Mizuho Information & Research Institute, Inc. (MHIR) 2-3 Kanda-Nishikicho, Chiyoda-ku, Tokyo 101-8443, Japan *** Mitsubishi Heavy Industries, Ltd. (MHI) 1-1-1 Wadasaki-cho, Hyogo-ku, Kobe, Hyogo, 652-8585, Japan **** IHI Corporation (IHI) 1 Sinnakahara, Isogo, Yokohama, Kanagawa 235-8501, Japan † Central Research Institute of Electric Power Industry (CRIEPI) 2-6-1 Nagasaka, Yokosuka, Kanagawa 240-0196, Japan †† Nagaoka University of Technology (NUT) 1603 Kamitomioka, Nagaoka, Niigata 940-2188, Japan ††† Ibaraki University 4-12-1 Nakanarusawa, Hitachi, Ibaraki 316-8511, Japan

Recent verification activities on probabilistic fracture mechanics analysis code PASCAL4 for reactor pressure vessel