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Vol.11 No.4previousAA SP22 (AA165-166-167-168-169-170-171) NT96

Academic Articles
Regular Paper Vol. 11 No. 4 (2020) p.172 - p.178

Verification of Safety Margin of Reactor Pressure Vessel Exposed to Various Thermal Transients Based on Probabilistic Approach


Masahide SUZUKI1, Kenta MURAKAMI1, Takashi SUZUKI1*, Ryuta OKAYAMA1**, Jinya KATSUYAMA2 and Yinsheng LI2

1 Nagaoka University of Technology, Kamitomioka 1603-1, Nagaoka, Niigata, 940-2188, Japan
1* Formerly graduate student, currently Japan Nuclear Fuel Limited,
1** Formerly graduate student, currently Tokyo Electric Power Company,
2 Japan Atomic Energy Agency, Tokai-mura, Nakagun, Ibaraki, 319-1195, Japan
For the reactor pressure vessel (RPV) integrity assessment, deterministic fracture mechanics (DFM) is applied considering factors such as neutron irradiation embrittlement, postulated crack and thermals transients etc. On the other hand, probabilistic fracture mechanics (PFM) can evaluate the failure probability considering the uncertainties of several kinds of factors affecting the RPV integrity. The purpose of present study is to obtain insight concerning the further improvement of RPV structural integrity from the probabilistic approach consideration through careful comparisons with DFM approach. It was found that the transients which give rise to the re-pressurization have a possibility to deteriorate the deterministic – probabilistic correlation to some extent.
Reactor Pressure Vessel, Probabilistic Fracture Mechanics, Pressurized Thermal Shock, Structural Integrity, Irradiation Embrittlement, Fracture Toughness, Thermal Transients
Full Paper: PDF
Article Information
Article history:
Received 5 December 2018
Accepted 28 February 2020