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

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dc.contributor.advisorKorukonda Murty, Chair
dc.contributor.advisorRonald Scattergood, Member
dc.contributor.advisorMohamed Bourham, Member
dc.contributor.advisorGe Yang, Member
dc.contributor.authorAlsmadi, Zeinab Yousef Mohammad
dc.date.accepted2020-03-20
dc.date.accessioned2020-03-21T12:30:53Z
dc.date.available2020-03-21T12:30:53Z
dc.date.defense2020-03-09
dc.date.issued2020-03-09
dc.date.released2020-03-21
dc.date.reviewed2020-03-16
dc.date.submitted2020-03-13
dc.degree.disciplineNuclear Engineering
dc.degree.leveldissertation
dc.degree.nameDoctor of Philosophy
dc.descriptionNorth Carolina State University Theses Nuclear Engineering.
dc.formatPh.D. North Carolina State University, 2020.
dc.identifier.otherdeg20340
dc.identifier.urihttps://www.lib.ncsu.edu/resolver/1840.20/37277
dc.titleHigh Temperature Creep-Fatigue Behavior of Alloy 709 Austenitic Stainless Steel in Sodium-Cooled Fast Reactors.
dcterms.extent1 online resource (xv, 187 pages) : illustrations (some color)

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