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Dislocation-Radiation Obstacle Interactions: Developing Improved Mechanical Property Constitutive Models, Final.

DE2008920995

Publication Date	2007
Personal Author	WIrth, B. D.; Robertson, I. M.
Page Count	23
Abstract	Radiation damage to structural and cladding materials, including austenitic stainless steels, ferritic steels, and zirconium alloys, in nuclear reactor environments results in significant mechanical property degradation, including yield strength increases, severe ductility losses and flow localization, which impacts reliability and performance. Generation IV and advanced fuel cycle concepts under consideration will require the development of advanced structural materials, which will operate in increasingly hostile environments. The development of predictive models is required to assess the performance and response of materials in extreme Gen IV reactor operating conditions (temperature, stress, and pressure), to decrease the time to rapidly assess the properties of new materials and insert them into technological applications (Gen IV and Advanced Fuel Cycle Operations).
Keywords	Radiation damage Nuclear reactors Building materials Ductility Ferritic steels Fuel cycles Performance Reliability Stainless steels Yield strength Zirconium alloys Predictive models Radiation
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	California Univ., Berkeley. Dept. of Mineral Engineering and Materials Science.; Department of Energy, Washington, DC.; Illinois Univ. at Urbana-Champaign. Dept. of Materials Science and
Supplemental Notes	Prepared in cooperation with Illinois Univ. at Urbana-Champaign. Dept. of Materials Science and Engineering. Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200814
Contract Number	FG07-04ID14594

Dislocation-Radiation Obstacle Interactions: Developing Improved Mechanical Property Constitutive Models, Final.

Dislocation-Radiation Obstacle Interactions: Developing Improved Mechanical Property Constitutive Models, Final.
DE2008920995

Publication Date	2007
Personal Author	WIrth, B. D.; Robertson, I. M.
Page Count	23
Abstract	Radiation damage to structural and cladding materials, including austenitic stainless steels, ferritic steels, and zirconium alloys, in nuclear reactor environments results in significant mechanical property degradation, including yield strength increases, severe ductility losses and flow localization, which impacts reliability and performance. Generation IV and advanced fuel cycle concepts under consideration will require the development of advanced structural materials, which will operate in increasingly hostile environments. The development of predictive models is required to assess the performance and response of materials in extreme Gen IV reactor operating conditions (temperature, stress, and pressure), to decrease the time to rapidly assess the properties of new materials and insert them into technological applications (Gen IV and Advanced Fuel Cycle Operations).
Keywords	Radiation damage Nuclear reactors Building materials Ductility Ferritic steels Fuel cycles Performance Reliability Stainless steels Yield strength Zirconium alloys Predictive models Radiation
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	California Univ., Berkeley. Dept. of Mineral Engineering and Materials Science.; Department of Energy, Washington, DC.; Illinois Univ. at Urbana-Champaign. Dept. of Materials Science and
Supplemental Notes	Prepared in cooperation with Illinois Univ. at Urbana-Champaign. Dept. of Materials Science and Engineering. Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200814
Contract Number	FG07-04ID14594