Radiation Induced Microstructural Evolution in Reactor Pressure Vessel Steels

1994 ◽  
Vol 373 ◽  
Author(s):  
G. R. Odette

AbstractThe evolution of the fine scale microstructural features leading to irradiation embrittlement of reactor pressure vessel steels is described. Copper rich phases undergo accelerated precipitation from supersaturated solution due to radiation enhanced diffusion. In steels with significant trace quantities of copper the precipitates, characterized by high concentrations and small sizes, are the dominant embrittling feature. Precipitate concentrations, sizes, volume fractions and compositions are consistent with thermodynamic and kinetic models that rationalize the effects of a number of irradiation and metallurgical variables. Phosphide and carbonitride phases may also develop along with new manganese nickel rich precipitates, promoted by high nickel contents. These features may lead to severe embrittlement at high fluence even in low copper steels. While their detailed identity and characteristics are not known, defect cluster-solute complexes with a range of thermal stability are important both directly and indirectly; for example, in mediating flux and temperature effects. In conjunction with the application of state-of-the-art characterization methods, development of advanced modeling tools will be needed to address a number of outstanding issues.

1998 ◽  
Vol 47 (11) ◽  
pp. 1112-1118
Author(s):  
Sumio MURAKAMI ◽  
Atsushi MIYAZAKI ◽  
Kazuki TSUGIHASHI ◽  
Mamoru MIZUNO ◽  
Morio JINCHO ◽  
...  

1997 ◽  
Vol 46 (2) ◽  
pp. 124-130
Author(s):  
Sumio MURAKAMI ◽  
Kazuki TSUGIHASHI ◽  
Atsushi MIYAZAKI ◽  
Morio JINCHO ◽  
Tetsuya SUZUKI

1999 ◽  
Vol 122 (1) ◽  
pp. 60-66 ◽  
Author(s):  
S. Murakami ◽  
A. Miyazaki ◽  
M. Mizuno

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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