Preliminary safety evaluation of a supercritical carbon...

Nuclear Engineering and Design 2020 / 12 Vol. 369

Preliminary safety evaluation of a supercritical carbon dioxide Brayton cycle cooled reactor system under loss-of-flow accident

Wu, Pan, Liu, Weihua, Gao, Chuntian, Ma, Yunduo, Shan, Jianqiang
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Volume:
369
Journal:
Nuclear Engineering and Design
DOI:
10.1016/j.nucengdes.2020.110860
Date:
December, 2020
File:
PDF, 7.67 MB
2020
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