Embrittlement and Flow Localization of Reactor Structural Materials
Wu, Xianglin
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Permalink
https://hdl.handle.net/2142/85913
Description
Title
Embrittlement and Flow Localization of Reactor Structural Materials
Author(s)
Wu, Xianglin
Issue Date
2007
Doctoral Committee Chair(s)
Stubbins, James F.
Department of Study
Nuclear Engineering
Discipline
Nuclear Engineering
Degree Granting Institution
University of Illinois at Urbana-Champaign
Degree Name
Ph.D.
Degree Level
Dissertation
Keyword(s)
Engineering, Materials Science
Language
eng
Abstract
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.
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