Irradiation Embrittlement of Reactor Pressure Vessel Steels due to Mechanisms Other than Radiation Hardening

2009 ◽  
pp. 271-271-25 ◽  
Author(s):  
BA Gurovich ◽  
YN Korolev ◽  
EA Kuleshova ◽  
YA Nikolaev ◽  
YI Shtrombakh
Keyword(s):  
Pressure Vessel ◽  
Reactor Pressure Vessel ◽  
Radiation Hardening ◽  
Irradiation Embrittlement ◽  
Pressure Vessel Steels ◽  
Reactor Pressure

scholarly journals Mechanisms and Modeling of Irradiation Embrittlement of Reactor Pressure Vessel Steels.

1998 ◽  
Vol 47 (11) ◽  
pp. 1112-1118
Author(s):  
Sumio MURAKAMI ◽  
Atsushi MIYAZAKI ◽  
Kazuki TSUGIHASHI ◽  
Mamoru MIZUNO ◽  
Morio JINCHO ◽  
...  
Keyword(s):  
Pressure Vessel ◽  
Reactor Pressure Vessel ◽  
Irradiation Embrittlement ◽  
Pressure Vessel Steels ◽  
Reactor Pressure

scholarly journals Modeling of Irradiation Embrittlement of Reactor Pressure Vessel Steels

1997 ◽  
Vol 46 (2) ◽  
pp. 124-130
Author(s):  
Sumio MURAKAMI ◽  
Kazuki TSUGIHASHI ◽  
Atsushi MIYAZAKI ◽  
Morio JINCHO ◽  
Tetsuya SUZUKI
Keyword(s):  
Pressure Vessel ◽  
Reactor Pressure Vessel ◽  
Irradiation Embrittlement ◽  
Pressure Vessel Steels ◽  
Reactor Pressure

Modeling of Irradiation Embrittlement of Reactor Pressure Vessel Steels

1999 ◽  
Vol 122 (1) ◽  
pp. 60-66 ◽  
Author(s):  
S. Murakami ◽  
A. Miyazaki ◽  
M. Mizuno
Keyword(s):  
Yield Stress ◽  
Neutron Irradiation ◽  
Pressure Vessel ◽  
Void Nucleation ◽  
Reactor Pressure Vessel ◽  
Material Behavior ◽  
Uniaxial Tensile ◽  
Irradiation Embrittlement ◽  
Pressure Vessel Steels ◽  
Reactor Pressure

A model to describe the change in the inelastic and fracture properties of reactor pressure vessel steels due to neutron irradiation in the ductile region (i.e., irradiation embrittlement) is developed. First, constitutive equations for unirradiated elastic-viscoplastic-damaged materials are developed within the framework of the irreversible thermodynamics theory. To take into account the effect of hydrostatic pressure on the nucleation and growth of microvoids, properly defined dissipation potential is used. Then, the effect of irradiation on the material behavior is incorporated into the proposed model as a function of neutron fluence Φ by taking into account the interaction between irradiation-induced defects and movable dislocations. As regards the damage strain threshold pD, the mechanism of void nucleation due to pile-up of dislocations at the inclusions in the material is proposed first under unirradiated-condition, and then the effect of irradiation on the mechanism is formulated. In order to demonstrate the validity of this model, it is applied to the case of uniaxial tensile loading of a low alloy steel A533B cl. 1 for the pressure vessel use of light-water reactors at 260°C. The resulting model can describe the increase in yield stress and ultimate tensile strength, the decrease in total elongation and strain hardening, and the strain rate dependence of yield stress due to neutron irradiation. [S0094-4289(00)00901-4]

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