Radiation embrittlement modelling for reactor pressure vessel steels: I. Brittle fracture toughness prediction

1999 ◽  
Vol 76 (10) ◽  
pp. 715-729 ◽  
Author(s):  
B.Z. Margolin ◽  
V.A. Shvetsova ◽  
A.G. Gulenko
Keyword(s):  
Fracture Toughness ◽  
Brittle Fracture ◽  
Pressure Vessel ◽  
Reactor Pressure Vessel ◽  
Radiation Embrittlement ◽  
Pressure Vessel Steels ◽  
Reactor Pressure

The Effect of Radiation-Induced Structural Changes under Accelerated Irradiation on the Behavior of Water-Cooled Reactor Pressure Vessel Steels

2013 ◽  
Vol 592-593 ◽  
pp. 573-576 ◽  
Author(s):  
Boris A. Gurovich ◽  
Evgenia A. Kuleshova ◽  
Dmitry A. Maltsev ◽  
Oleg Zabusov ◽  
Kirill Prikhodko ◽  
...  
Keyword(s):  
Pressure Vessel ◽  
Structural Changes ◽  
Structural Features ◽  
Reactor Pressure Vessel ◽  
Fast Neutron Flux ◽  
Radiation Embrittlement ◽  
Pressure Vessel Steels ◽  
Radiation Induced ◽  
Hardening Mechanisms ◽  
Reactor Pressure

In this paper the influence of fast neutron flux on the structural features and properties of VVER-1000 reactor pressure vessel steels was studied. It is shown that for high Ni steels the flux effect is due to hardening and non-hardening mechanisms of radiation embrittlement.

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.

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