Development of a thermal–mechanical behavior coupling analysis code for a dual-cooled annular fuel element in PWRs
Title of Paper:
Development of a thermal–mechanical behavior coupling analysis code for a dual-cooled annular fuel element in PWRs
Journal:
Nuclear Engineering and Design
Summary:
Development of a thermal–mechanical behavior coupling analysis code for a dual-cooled annular fuel element in PWRs
Co-author:
Yangbin Deng, Yingwei Wu*, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su