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Vol.7 No.2previous AASP15 (106-107-108-109-110-111)- AA112-113 NT71

Academic Articles
Regular Paper Vol.7 No.2 (2015) p.166 - p.171

Fracture Toughness Curves of Japanese Reactor Pressure Vessel Steels considering Neutron Irradiation Embrittlement

Kentaro YOSHIMOTO 1, Takatoshi HIROTA 2, Hiroyuki SAKAMOTO 2

1 Mitsubishi Heavy Industries, Ltd. 1-1 Arai-cho Shinhama 2-chome Takasago, 676-8686, Japan
2 Mitsubishi Heavy Industries, Ltd.1-1 Wadasaki-cho 1-chome, Hyogoku, Kobe, 652-8585, Japan


In Japanese nuclear power plants, surveillance tests are conducted according to the Japan Electric Association Code JEAC4201 in order to monitor the degree of embrittlement of reactor pressure vessel (RPV) material due to neutron irradiation. Through the surveillance tests for Pressurized Water Reactor (PWR) plants, a large number of fracture toughness data have been accumulated for Japanese RPV irradiated materials. New fracture toughness curves have been developed adopting the Master Curve (MC) concept and these curves have been correlated with the Charpy V-notch 30 ft-lb transition temperature, Tr30 for evaluation against Pressurized Thermal Shock (PTS) events. The developed curves are also intended to represent the 5% tolerance lower bound of fracture toughness trend incorporating fracture toughness variation depending on the product form, which consists of plates, forgings and weld metals. In this study, the reliability of the curves is evaluated for predicted Tr30 values in consideration of application to PTS evaluation for Japanese PWR plants and it was demonstrated that the developed lower bound curve has reliability comparable to that for the measured Tr30 by adding a margin of 3 ºC to the predicted Tr30.

Fracture Toughness, Master Curve, Reactor Pressure Vessel
Full Paper: PDF EJAM Vol.7No.2 pp.166-171 "Fracture Toughness Curves of Japanese Reactor Pressure Vessel Steels considering Neutron Irradiation Embrittlement"
Article Information
Article history:
Received 21 November 2014
Accepted 22 June 2015