b'Development of anHigh-throughput corrosion-fatigue testing capability and expertise will help Innovative Testingcurrent reactor lifetime extension and advanced reactor deployment.Framework to Assess CrackC rack initiation and growth in-reactor structural materials under cyclic loading (fatigue) are aggravated by the presence of a corrosive Initiation Assisted byenvironment. To qualify a material for reactor operation, its susceptibility Corrosion-Fatigue to environmental degradation must be assessed. Assessing material susceptibility to cracking from irradiation-assisted stress corrosion cracking and corrosion fatigue is a growing concern within the nuclear industry and has been identified by the U.S. Nuclear Regulatory Commission, Electric Power Research Institute, and other industry experts as a knowledge gap of high significance for the nuclear community. INL currently has heavily shielded state-of-the-art irradiation-assisted stress corrosion TOTAL APPROVED AMOUNT:cracking testing capabilities, and there are similar low activity facilities within the $125,000 over 1 year U.S. (e.g., the University of Michigan and the Pacific Northwest National Laboratory). However, no facilities in the U.S. are currently capable of assessing irradiation-PROJECT NUMBER:assisted corrosion fatigue of materials in a simulated corrosive environment like that 20A1052-025 of a boiling water reactor or pressurized water reactor. To demonstrate this technique, PRINCIPAL INVESTIGATOR:researchers developed an innovative corrosion-fatigue testing framework capable Boopathy Kombaiah of testing multiple specimens at a time providing a cost-efficient and accelerated routine to obtain statistical analysis of materials behavior.CO-INVESTIGATORS:Colin Judge, INL Researchers designed and produced a corrosion-fatigue fixture that is capable of Michael Heighes, INL multiple specimen tests at a time and applied the direct current potential drop method to detect any crack initiation and propagation that occur during cyclic loading. Furthermore, this proof-of-concept study investigated the susceptibility of a non-irradiated austenitic alloy to crack initiation under cyclic loading and attempted to demonstrate the capability to detect crack initiation using the direct current potential drop method. This new capability advances INLs ability to test structural materials. Next steps include adopting the corrosion-fatigue testing inside hot cells to support the accelerated development of advanced structural materials for nuclear reactor applications.PRESENTATION:Song, R., M. McMurtrey, B. Kombaiah,D. Johnson, M. Heighes, P. Xu, and C. Judge, Environmentally assisted cracking: Theory and practice, The Minerals, Metals & Materials Society 2022 Annual Meeting & Exhibition, Anaheim, CA, USA, Feb. 27Mar. 3, 2022.Corrosion-fatigue fixture during testing.46'