High Temperature Creep-Fatigue Behavior of Alloy 709 Austenitic Stainless Steel in Sodium-Cooled Fast Reactors.

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Title: High Temperature Creep-Fatigue Behavior of Alloy 709 Austenitic Stainless Steel in Sodium-Cooled Fast Reactors.
Author: Alsmadi, Zeinab Yousef Mohammad
Advisors: Korukonda Murty, Chair
Ronald Scattergood, Member
Mohamed Bourham, Member
Ge Yang, Member
Date: 2020-03-09
Degree: Doctor of Philosophy
Discipline: Nuclear Engineering
URI: https://www.lib.ncsu.edu/resolver/1840.20/37277


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