scholarly journals Micromechanical Modeling of Ductile Fracture Initiation to Predict Fracture Toughness of Reactor Pressure Vessel Steels

1996 ◽  
Vol 06 (C6) ◽  
pp. C6-53-C6-64 ◽  
Author(s):  
R. Chaouadi ◽  
P. De Meester ◽  
M. Scibetta
Keyword(s):  
Fracture Toughness ◽  
Ductile Fracture ◽  
Pressure Vessel ◽  
Fracture Initiation ◽  
Reactor Pressure Vessel ◽  
Micromechanical Modeling ◽  
Pressure Vessel Steels ◽  
Ductile Fracture Initiation ◽  
Reactor Pressure

Master Curve Approach for Some Japanese Reactor Pressure Vessel Steels

2008 ◽  
Author(s):  
Minoru Tomimatsu ◽  
Takashi Hirano ◽  
Seiji Asada ◽  
Ryoichi Saeki ◽  
Naoki Miura ◽  
...  
Keyword(s):  
Fracture Toughness ◽  
Power Plant ◽  
Pressure Vessel ◽  
Nuclear Power ◽  
Master Curve ◽  
Reactor Pressure Vessel ◽  
Pressure Vessel Steels ◽  
The World ◽  
Reactor Pressure ◽  
Plant Components

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.

scholarly journals JIC Fracture Toughness of Nuclear Reactor Pressure Vessel Steels in Transition and Upper Shelf Regions

1982 ◽  
Vol 68 (8) ◽  
pp. 1032-1039 ◽  
Author(s):  
Tsuneo KODAIRA ◽  
Nobuya NAKAJIMA ◽  
Masakatsu MATSUMOTO ◽  
Kiyoshi FUKAYA
Keyword(s):  
Fracture Toughness ◽  
Pressure Vessel ◽  
Nuclear Reactor ◽  
Reactor Pressure Vessel ◽  
Pressure Vessel Steels ◽  
Reactor Pressure
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