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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

Chain of custody

source
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
related terms
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

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