Microstructural characterization of cold-worked 316 stainless steel flux thimble tubes irradiated up to 100 dpa in a commercial Pressurized Water Reactor

Author:

Song Miao,Field Kevin G.,Cox Richard M,Was Gary S.

Funder

U.S. Department of Energy

Electric Power Research Institute

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference42 articles.

1. Radiation-induced degradation of stainless steel light water reactor internals;Kenik;Mater. Sci. Eng. R Rep.,2012

2. Using fast reactor component evaluation for pressurized water reactor life extension;Allen;J. Occup. Med.,1999

3. Microstructural characterization and density change of 304 stainless steel reflector blocks after long-term irradiation in EBR-II;Huang;J. Nucl. Mater.,2015

4. Alloying effect of Ni and Cr on irradiated microstructural evolution of type 304 stainless steels;Tan;J. Nucl. Mater.,2013

5. Microstructural evolution of type 304 and 316 stainless steels under neutron irradiation at LWR relevant conditions;Tan;J. Occup. Med.,2016

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