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

Alsmadi, Zeinab Yousef Mohammad

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North Carolina State University

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

dc:creator Alsmadi, Zeinab Yousef Mohammad

dc:date.issued2020

Abstract

dc:description

North Carolina State University Theses Nuclear Engineering.

Author and committee

dc:creator, dc:contributor.*

Author dc:creator: Alsmadi, Zeinab Yousef Mohammad
Advisors dc:contributor.advisor: Korukonda Murty, Chair
Ronald Scattergood, Member
Mohamed Bourham, Member
Ge Yang, Member

Identifiers

dc:identifier.*

Dc Identifier Other: deg20340
OAI record oai:identifier: https://repository.lib.ncsu.edu/server/oai/request?verb=GetRecord&metadataPrefix=dim&identifier=oai%3Arepository.lib.ncsu.edu%3A1840.20%2F37277

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Harvested from: North Carolina State University
Base URL: repository.lib.ncsu.edu/server/oai/request
Last updated: 2026-08-21
Source record: OAI-PMH GetRecord

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ncsu
2020

citation

Alsmadi, Zeinab Yousef Mohammad. High Temperature Creep-Fatigue Behavior of Alloy 709 Austenitic Stainless Steel in Sodium-Cooled Fast Reactors.. 2020. https://www.lib.ncsu.edu/resolver/1840.20/37277

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

Abstract

Author and committee

Identifiers

Chain of custody

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