Review of uncertainty analysis in sodium-cooled fast reactor systems
Special Issue on The First Academic Annual Conference of the Research Reactor and Innovative Reactor Association of Chinese Nuclear Society and Advanced Nuclear Power System Reactor Engineering|更新时间:2025-08-19
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Review of uncertainty analysis in sodium-cooled fast reactor systems
“Progress has been made in uncertainty analysis of sodium cooled fast reactor systems, providing reference for safety assessment and design optimization of nuclear energy systems.”
ZHANG Zhe, male, born in 1988, graduated from Hunan University with a doctoral degree in 2016, focusing on uncertainty analysis and design
JIANG Chao, E-mail: jiangc@hnu.edu.cn
基金信息:
National Natural Science Foundation of China(52375242);Science and Technology Innovation Program of Hunan Province(2024RC3112);Natural Science Foundation and Outstanding Youth Foundation of Hunan Province(2023JJ20011)
ZHANG Zhe,CHEN Yi,JIN Desheng,et al.Review of uncertainty analysis in sodium-cooled fast reactor systems[J].NUCLEAR TECHNIQUES,2025,48(07):070007-070007.