Characterization of Decommissioned PWR Vessel Internals Material Samples. Tensile and SSRT Testing (Nonproprietary Version). Technical Report.

Technical Information Center Oak Ridge Tennessee

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

RP-ID  :  DE2005837206

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 requires detailed knowledge of the changes in mechanical and corrosion properties of the structural austenitic stainless steel components adjacent to the fuel (internals) subjected to such conditions. This project studied the effects of reactor service on the mechanical and corrosion properties of samples of baffle plate, former plate, and core barrel from a decommissioned PWR.