This review paper examines mechanisms controlling IGSCC in selected LWR components. Emphasis is placed on identifying material microstructures and microchemistries which promote susceptibility to premature failure. Two important examples are evaluated in some detail: stainless steel pipe cracking and primary-side SCC of alloy 600 steam generator tubing. In each case, grain boundary segregation and precipitation phenomena in these materials are reviewed and assessed relative to the mechanisms of IGSCC. This paper summarizes materials presented at the 1993 International Summer School on the Fundamentals of Radiation Damage held at the University of Illinois. A more comprehensive overview of SCC mechanisms and LWR examples was provided at the ...
Irradiation-assisted stress corrosion cracking (IASCC) occurs above a critical neutron fluence in li...
Stress corrosion cracking in piping welds in boiling water reactors (BWR's) has been observed in sta...
Intergranular stress corrosion cracking (IGSCC) is common in boiling water reactor (BWR) components....
Intergranular stress corrosion cracking (IASCC) is a pervasive and generic problem in current light ...
Intergranular stress corrosion cracking (SCC) of austenitic stainless steel components is a life-lim...
Irradiation-assisted stress corrosion cracking is a costly degradation mechanism for austenitic stai...
The overall goal of the project is to determine the mechanism of irradiation assisted stress corrosi...
Environmentally assisted cracking (EAC) of lightwater reactor (LWR) materials has affected nuclear r...
Recently intergranular stress corrosion cracking (IGSCC) in austenitic stainless steel 316L of Prima...
Certain safety-related core internal structural components of light water reactors, usually fabricat...
The objective of this study was to determine how the deformation propensities of individual grains o...
This chapter focuses on intergranular and transgranular stress corrosion cracking (IGSCC and TGSCC) ...
OAK-B135 An Investigation of the Mechanism of IGA/SCC of Alloy 600 in Corrosion Accelerating Heated ...
International audienceIrradiation Assisted Stress Corrosion Cracking (IASCC) is a material degradati...
Cracking behavior of stainless steels specimens irradiated in the BOR-60 at about 320 C is studied. ...
Irradiation-assisted stress corrosion cracking (IASCC) occurs above a critical neutron fluence in li...
Stress corrosion cracking in piping welds in boiling water reactors (BWR's) has been observed in sta...
Intergranular stress corrosion cracking (IGSCC) is common in boiling water reactor (BWR) components....
Intergranular stress corrosion cracking (IASCC) is a pervasive and generic problem in current light ...
Intergranular stress corrosion cracking (SCC) of austenitic stainless steel components is a life-lim...
Irradiation-assisted stress corrosion cracking is a costly degradation mechanism for austenitic stai...
The overall goal of the project is to determine the mechanism of irradiation assisted stress corrosi...
Environmentally assisted cracking (EAC) of lightwater reactor (LWR) materials has affected nuclear r...
Recently intergranular stress corrosion cracking (IGSCC) in austenitic stainless steel 316L of Prima...
Certain safety-related core internal structural components of light water reactors, usually fabricat...
The objective of this study was to determine how the deformation propensities of individual grains o...
This chapter focuses on intergranular and transgranular stress corrosion cracking (IGSCC and TGSCC) ...
OAK-B135 An Investigation of the Mechanism of IGA/SCC of Alloy 600 in Corrosion Accelerating Heated ...
International audienceIrradiation Assisted Stress Corrosion Cracking (IASCC) is a material degradati...
Cracking behavior of stainless steels specimens irradiated in the BOR-60 at about 320 C is studied. ...
Irradiation-assisted stress corrosion cracking (IASCC) occurs above a critical neutron fluence in li...
Stress corrosion cracking in piping welds in boiling water reactors (BWR's) has been observed in sta...
Intergranular stress corrosion cracking (IGSCC) is common in boiling water reactor (BWR) components....