Characterization of Creep-Fatigue Crack Growth in Alloy 709 and Prediction of Service Lives in Nuclear Reactor Components - University of Idaho CX(s) Applied: B3.6Date: 06/29/2015 Location(s): IdahoOffices(s): Nuclear Energy
Office of NEPA Policy and Compliance
June 29, 2015
Estimated Read Time min
Characterization of Creep-Fatigue Crack Growth in Alloy 709 and Prediction of Service Lives in Nuclear Reactor Components - University of Idaho
CX(s) Applied: B3.6
Date: 06/29/2015
Location(s): Idaho
Offices(s): Nuclear Energy
The University of Idaho proposes 1) to measure and report the creep-fatigue crack growth rates in Alloy 709 under various creep-fatigue loading in accelerated test conditions and to use this knowledge to predict the extended service life of structural components, 2) to measure and report the creep-fatigue crack growth rates in Alloy 709 in as-received and aged conditions, and to identify extrapolation rules between these conditions, and 3) to develop and provide a flaw evaluation procedure under creep-fatigue service conditions.