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Master Curve Approach for Some Japanese Reactor Pressure Vessel Steels

[+] Author Affiliations
Minoru Tomimatsu, Seiji Asada

Mitsubishi Heavy Industries Ltd., Kobe, Japan

Takashi Hirano

IHI Corporation, Yokohama, Japan

Ryoichi Saeki

Toshiba Corporation, Yokohama, Japan

Naoki Miura

Central Research Institute of Electric Power Industry, Komae, Japan

Norimichi Yamashita

Tokyo Electric Power Company, Inc., Tokyo, Japan

Akira Yonehara

The Kansai Electric Power Co., Inc., Osaka, Japan

Itaru Saito

Japan Nuclear Technology Institute, Tokyo, Japan

Paper No. PVP2008-61494, pp. 855-862; 8 pages
doi:10.1115/PVP2008-61494
From:
  • ASME 2008 Pressure Vessels and Piping Conference
  • Volume 6: Materials and Fabrication, Parts A and B
  • Chicago, Illinois, USA, July 27–31, 2008
  • Conference Sponsors: Pressure Vessels and Piping
  • ISBN: 978-0-7918-4829-6
  • Copyright © 2008 by ASME

abstract

The Master Curve Approach for assessing fracture toughness of reactor pressure vessel (RPV) steels has been accepted throughout the world. The Master Curve Approach using fracture toughness data obtained from RPV steels in Japan has been investigated in order to incorporate this approach into the Japanese Electric Association (JEA) Code 4206, “Method of Verification Tests of the Fracture Toughness for Nuclear Power Plant Components”. This paper presents the applicability of the Master Curve Approach for Japanese RPV steels.

Copyright © 2008 by ASME

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