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

Krug, M. ; Shogan, R. ; Fero, A.

Technical Information Center Oak Ridge Tennessee

关键词: Reactor internals;    PWR type reactors;    Nuclear reactor materials;    Radiation effects;    Characterization;   

RP-ID  :  DE2005836105

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports Library

【 摘 要 】

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.