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

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

Probabilistic fracture mechanics (PFM) is considered a promising methodology in assessing the integrity of structural components in nuclear power plants because it can rationally represent the influence parameters in their probabilistic distributions without over-conservativeness. In Japan, Japan At...

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Bibliographic Details
Main Authors: Kai LU, Jinya KATSUYAMA, Yinsheng LI, Yuhei MIYAMOTO, Takatoshi HIROTA, Yu ITABASHI, Masaki NAGAI, Masahide SUZUKI, Yasuhiro KANTO
Format: article
Language:EN
Published: The Japan Society of Mechanical Engineers 2020
Subjects:
structural integrity assessment
probabilistic fracture mechanics
reactor pressure vessel
neutron irradiation embrittlement
pressurized thermal shock
Mechanical engineering and machinery
TJ1-1570
Online Access:https://doaj.org/article/a0cb1ac09d11407d8a3bd69bd0f2080e
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https://doaj.org/article/a0cb1ac09d11407d8a3bd69bd0f2080e

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