Embrittlement and Flow Localization of Reactor Structural Materials

Wu, Xianglin
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http://hdl.handle.net/2142/85913

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Title:Embrittlement and Flow Localization of Reactor Structural Materials
Author(s):Wu, Xianglin
Doctoral Committee Chair(s):Stubbins, James F.
Department / Program:Nuclear Engineering
Discipline:Nuclear Engineering
Degree Granting Institution:University of Illinois at Urbana-Champaign
Degree:Ph.D.
Genre:Dissertation
Subject(s):Engineering, Materials Science
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.
Issue Date:2007
Type:Text
Language:English
Description:174 p.
Thesis (Ph.D.)--University of Illinois at Urbana-Champaign, 2007.
URI:http://hdl.handle.net/2142/85913
Other Identifier(s):(MiAaPQ)AAI3270055
Date Available in IDEALS:2015-09-28
Date Deposited:2007


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