Irradiation-assisted stress corrosion cracking(IASCC) susceptibility was measured for 316 stainlesssteel irradiated in the BOR-60 liquid sodium fast reactorat a temperature of 320°C to 46.9 and 67.4 dpa. IASCCinitiation susceptibility was determined using interruptedconstant extension rate tensile (CERT) tests and a strainrate of 3.5×10~(-7) s~(-1) under simulated PWR primary waterenvironment. Specimens were strained to varyingfractions of the yield strength starting at 40%, and cracksaccompanied by discontinuous dislocation channels wereobserved near their yield stress. The total elongation andreduction of area of the specimens decreased with dose,while fraction of intergranular fracture increased.
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