Tag Archives: Irradiation-assisted stress corrosion cracking (IASCC)
Traditional heat treatments used in production of parts made of alloy 718 may not be optimal for the corrosive, irradiated environment of pressurized water reactors, potentially leading to fuel assembly component degradation. This study evaluated 11 different thermo-mechanical treatments for alloy 718 for their ability to reduce susceptibility to stress corrosion cracking and irradiation-assisted stress […]
Establishment of the Capability to Determine Irradiation-Assisted Stress Corrosion Cracking Initiation from Four-Point Bend Tests Conducted in a Boiling Water Reactor Normal Water Chemistry Environment
In this study, researchers developed and tested an experimental bend technique to better understand the mechanisms of irradiation-assisted stress corrosion cracking in austenitic steels in light water reactor core components.
Development of Small-Volume Mechanical Testing—Initial Application to Proton-Irradiated Stainless Steel
In this study, researchers developed and deployed mechanical tests to investigate degradation and failure in proton-irradiated stainless steel in light water nuclear reactor components.
Irradiation-Assisted Stress Corrosion Cracking Susceptibility and Evolution of Microstructure in Several Nickel-Base Alloys after Proton Irradiation
For long-term operations of existing nuclear plants and the design of next-generation plants, it is desirable to develop more radiation-resistant materials for reactor core components. This report describes the impacts of proton irradiation on four nickel-base alloys, with a focus on microstructure, irradiation hardening, and susceptibility to stress corrosion cracking. It was prepared as part […]