Irradiation Assisted Stress Corrosion Cracking (IASCC) of Nickel-Base Alloys in Light Water Reactors Environments Part II: Stress Corrosion Cracking
Radiation-induced microstructural changes control the Irradiation Assisted Stress Corrosion Cracking (IASCC) of core materials, which is a key factor in the extension of the operating lifetime of Light Water Reactors (LWRs). Nickel-base alloys are considered as potential structural materials to replace highly IASCC susceptible austenitic stainless steels. Constant extension rate tensile (CERT) tests were conducted on proton irradiated high strength nickel-base alloy 625 with two different heat treatment conditions (625Plus and 625DA) in both simulated BWR NWC and PWR primary water. Crack length per unit area and fraction of grain boundaries that cracked were used to assess the IASCC susceptibility. Both 625Plus and 625DA showed a very high IASCC susceptibility. 625DA also exhibited greater changes in all microstructure features than 625Plus.
KeywordsNickel-base alloys Irradiation-assisted stress corrosion cracking Mechanical properties LWRs
Support for this work was provided by the Electric Power Research Institute (contract no: 10002164 and 10002154) and Department of Energy (contract no: 4000136101). The authors gratefully acknowledge the facilities provided by the Michigan Ion Beam Laboratory and the High Temperature Corrosion Laboratory at the University of Michigan. The authors would also like to thank Dr. Ovidiu Toader of the Michigan Ion Beam Laboratory and Mr. Alex Flick of the High Temperature Corrosion Laboratory for their invaluable support in conducting the experiments.
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