Analysis of typical flow blockage accidents of single annular fuel assembly for lead-bismuth cooled fast reactor
NUCLEAR ENERGY SCIENCE AND ENGINEERING|更新时间:2024-10-25
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Analysis of typical flow blockage accidents of single annular fuel assembly for lead-bismuth cooled fast reactor
“In the field of nuclear energy, experts have established a 5 × 5 single box annular fuel assembly model to simulate and analyze flow blockage accidents in lead bismuth fast reactors, providing solutions to ensure nuclear safety.”
CHEN Qi, female, born in 2001, currently studying at the School of Nuclear Science and Technology, University of South China, focusing on thermal-hydraulic analysis of fast reactor
ZHAO Pengcheng, E-mail: zhaopengcheng1030@163.com
基金信息:
Science and Technology on Reactor System Design Technology Laboratory(KFKT-05-FW-HT-20220014)
CHEN Qi,LING Yufan,ZHAO Pengcheng,et al.Analysis of typical flow blockage accidents of single annular fuel assembly for lead-bismuth cooled fast reactor[J].NUCLEAR TECHNIQUES,2023,46(11):110602.
CHEN Qi,LING Yufan,ZHAO Pengcheng,et al.Analysis of typical flow blockage accidents of single annular fuel assembly for lead-bismuth cooled fast reactor[J].NUCLEAR TECHNIQUES,2023,46(11):110602. DOI: 10.11889/j.0253-3219.2023.hjs.46.110602.
Analysis of typical flow blockage accidents of single annular fuel assembly for lead-bismuth cooled fast reactor