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Li, Y.; Hirota, Takatoshi*; Itabashi, Yu*; Yamamoto, Masato*; Kanto, Yasuhiro*; Suzuki, Masahide*; Miyamoto, Yuhei*
JAEA-Review 2020-011, 130 Pages, 2020/09
JAEA-Review-2020-011.pdf:9.31MB
For the improvement of the structural integrity assessment methodology on reactor pressure vessels (RPVs), the probabilistic fracture mechanics (PFM) analysis code PASCAL has been developed and improved in Japan Atomic Energy Agency based on the latest knowledge. The PASCAL code evaluates the failure probabilities and frequencies of Japanese RPVs under transient events such as pressure thermal shock considering neutron irradiation embrittlement. In order to confirm the reliability of the PASCAL as a domestic standard code and to promote the application of PFM on the domestic structural integrity assessments of RPVs, it is important to perform verification activities, and summarize the verification processes and results as a document. On the basis of these backgrounds, we established a working group, composed of experts on this field besides the developers, on the verification of the PASCAL module and the source program of PASCAL was released to the members of working group. This report summarizes the activities of the working group on the verification of PASCAL in FY2016 and FY2017.
Takamizawa, Hisashi; Katsuyama, Jinya; Ha, Yoosung; Tobita, Toru; Nishiyama, Yutaka; Onizawa, Kunio
Proceedings of 2019 ASME Pressure Vessels and Piping Conference (PVP 2019) (Internet), 8 Pages, 2019/07
no abstracts in English
Ooka, Norikazu*; Ishii, Toshimitsu
Hihakai Kensa, 52(5), p.235 - 239, 2003/05
no abstracts in English
CNishiyama, Yutaka; Fukaya, Kiyoshi; Suzuki, Masahide; Eto, Motokuni
JAERI-Research 97-039, 29 Pages, 1997/06
JAERI-Research-97-039.pdf:1.41MB
no abstracts in English
Takamizawa, Hisashi; Hata, Kuniki; Hanawa, Satoshi; Nishiyama, Yutaka; Toyama, Takeshi*; Nagai, Yasuyoshi*
no journal, ,
no abstracts in English
Katsuyama, Jinya; Takamizawa, Hisashi; Ha, Yoosung; Nishiyama, Yutaka; Onizawa, Kunio
no journal, ,
We will present microstructure analysis results obtained by SEM and APT and so on for heat affected zone (HAZ) materials. The effects of microstructures such as grain size, phase fraction and martensite-austenite constituent on fracture toughness of HAZ materials were investigated. Also, the effects of solute cluster in the matrix and segregation near the carbide on irradiation embrittlement susceptibility will be discussed.
Hata, Kuniki; Iwata, Keiko; Shimodaira, Masaki; Ha, Yoosung; Takamizawa, Hisashi; Katsuyama, Jinya
no journal, ,
no abstracts in English
