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University of Illinois at Urbana-Champaign

Embrittlement and Flow Localization of Reactor Structural Materials

Abstract

dc:description

Notch effects have been analyzed utilizing finite element method (FEM) and EBSD misorientation map for unirradiated and irradiated 316L stainless steel. The major issue of interest is the possibility that low ductility, often found following irradiation exposure, will translate into low notch toughness. The influence of irradiation exposure can also lead to flow localization problems with components with notches or stress concentrators.

Degree

thesis:*
Name thesis:degree_name
Ph.D.
Level thesis:degree_level
Dissertation
Discipline thesis:degree_discipline
Nuclear Engineering
Grantor
University of Illinois at Urbana-Champaign
Year dc:date
2015

Author and committee

dc:creator, dc:contributor.*
Author dc:creator
  • Wu, Xianglin
Contributors dc:contributor
  • Stubbins, James F.

Subjects

dc:subject × 1

Rights

Language dc:language
eng

Identifiers

dc:identifier.*
Identifier
(MiAaPQ)AAI3270055
OAI identifier oai:identifier
oai:www.ideals.illinois.edu:2142/85913

Chain of custody

source
Harvested from
University of Illinois - Urbana-Champaign
Base URL
www.ideals.illinois.edu/oai-pmh
Last updated
2026-07-22
Source record
OAI-PMH GetRecord
citation

Wu, Xianglin. Embrittlement and Flow Localization of Reactor Structural Materials. Dissertation thesis, University of Illinois at Urbana-Champaign, 2015. http://hdl.handle.net/2142/85913