Safety analysis code development and validation for lead-cooled fast reactor with helical coiled once-through steam generator
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Published:2024-11
Issue:
Volume:207
Page:110719
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ISSN:0306-4549
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Container-title:Annals of Nuclear Energy
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language:en
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Short-container-title:Annals of Nuclear Energy
Author:
Zhang JiaxinORCID,
Wang Chenglong,
Tian Wenxi,
Su G.H,
Qiu Suizheng,
Xian Lin,
Cheng Kun,
Chu Xiao,
Wei Shiying,
Chen Guo