Analysis of warm prestressing effect on fracture toughness of reactor pressure vessel steels

2010 ◽  
Vol 42 (1) ◽  
pp. 120-123 ◽  
Author(s):  
R. Beleznai ◽  
Sz. Szávai
Author(s):  
Minoru Tomimatsu ◽  
Takashi Hirano ◽  
Seiji Asada ◽  
Ryoichi Saeki ◽  
Naoki Miura ◽  
...  

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.


1982 ◽  
Vol 68 (8) ◽  
pp. 1032-1039 ◽  
Author(s):  
Tsuneo KODAIRA ◽  
Nobuya NAKAJIMA ◽  
Masakatsu MATSUMOTO ◽  
Kiyoshi FUKAYA

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