Thesis Title: Aging Degradation Mechanisms of Alloy 709
Abstract: Currently there is an initiative by the Department of Energy (DOE) to qualify alloy 709 in the ASME pressure vessel code for use in the next generation of sodium fast nuclear reactors. Alloy 709 is based off NF709, which is an alloy produced by Nippon Steel. This project, initiated in August of 2015, will study and characterize the damage, creep mechanisms, and microstructural evolution of alloy 709 at stresses and temperatures present in a sodium fast reactor. Accelerating aging conditions will also be used to develop microstructures most likely present after 500,000 hours of reactor operations, and high temperature mechanical testing will be performed on these conditions. The assessment of damage and creep mechanisms will provide information that will be used in consideration of adding alloy 709 to the ASME code for use in these next generation nuclear reactors.
Degree Plan: Doctorate of Philosophy
Completion: Spring 2018
Group: Plate and Hot Rolled Steels
Steel Center Student Since: August 2015
Bio: Alan Carter joined the steel center in the fall of 2015. He received a bachelor’s degree in metallurgical and materials engineering from the Colorado School of mines in the spring of 2012. Between the years of 2012 and 2015 Alan Carter worked for Naval Reactors as a nuclear test engineer and was a qualified A4W propulsion plant shift test engineer.