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Characterization of Decommissioned PWR Vessel Internals Material Samples: Material Certification, Fluence, and Temperature (Nonproprietary Version).

DE2005836105

Publication Date	2004
Personal Author	Krug, M.; Shogan, R.; Fero, A.
Page Count	54
Abstract	Pressurized water reactor (PWR) cores, operate under extreme environmental conditions due to coolant chemistry, operating temperature, and neutron exposure. Extending the life of PWRs require detailed knowledge of the changes in mechanical and corrosion properties of the structural austenitic stainless steel components adjacent to the fuel. This report contains basic material characterization information of the as-installed samples of reactor internals material which were harvested from a decommissioned PWR.
Keywords	Reactor internals PWR type reactors Nuclear reactor materials Radiation effects Characterization Reactor components Austenitic stainless steels Chemical properties Mechanical properties Corrosion Materials tests Radiation exposure Thermal analysis Certification Fluence Temperature
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Electric Power Research Inst., Palo Alto, CA.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
Title Note	Technical rept.
NTIS Issue Number	200601

Characterization of Decommissioned PWR Vessel Internals Material Samples: Material Certification, Fluence, and Temperature (Nonproprietary Version).

Characterization of Decommissioned PWR Vessel Internals Material Samples: Material Certification, Fluence, and Temperature (Nonproprietary Version).
DE2005836105

Publication Date	2004
Personal Author	Krug, M.; Shogan, R.; Fero, A.
Page Count	54
Abstract	Pressurized water reactor (PWR) cores, operate under extreme environmental conditions due to coolant chemistry, operating temperature, and neutron exposure. Extending the life of PWRs require detailed knowledge of the changes in mechanical and corrosion properties of the structural austenitic stainless steel components adjacent to the fuel. This report contains basic material characterization information of the as-installed samples of reactor internals material which were harvested from a decommissioned PWR.
Keywords	Reactor internals PWR type reactors Nuclear reactor materials Radiation effects Characterization Reactor components Austenitic stainless steels Chemical properties Mechanical properties Corrosion Materials tests Radiation exposure Thermal analysis Certification Fluence Temperature
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Electric Power Research Inst., Palo Alto, CA.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
Title Note	Technical rept.
NTIS Issue Number	200601