Assessment of Aging Degradation Mechanisms of Alloy 709 for Sodium Fast Reactors - Colorado School of Mines CX(s) Applied: B3.6Date: 06/17/2015 Location(s): IdahoOffices(s): Nuclear Energy
Office of NEPA Policy and Compliance
June 17, 2015
Estimated Read Time min
Assessment of Aging Degradation Mechanisms of Alloy 709 for Sodium Fast Reactors - Colorado School of Mines
CX(s) Applied: B3.6
Date: 06/17/2015
Location(s): Idaho
Offices(s): Nuclear Energy
The Colorado School of Mines proposes to develop sufficient understanding of the mechanisms responsible for behavior of NF 709 under accelerated testing conditions to confidently predict long-term creep and creep-fatigue behavior at the times (500,000 hours) and temperatures (550o C) of interest for fast reactor structural applications.