ICONE29-92379 Thermal-Hydraulic Safety Analysis of Natural Circulation Lead-Cooled Fast Reactor SNCLFR-100 Core Based on Porous Medium Approach

ICONE29-92379 Thermal-Hydraulic Safety Analysis of Natural Circulation Lead-Cooled Fast Reactor SNCLFR-100 Core Based on Porous Medium Approach

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Veröffentlicht in:International Conference on Nuclear Engineering (29. : 2022 : Online) Proceedings of 2022 29th International Conference on Nuclear Engineering (ICONE 29) ; Volume 7, B
1. Verfasser: Feng, Wenpei (VerfasserIn)
Weitere Verfasser: Yang, Guangliang (VerfasserIn), Zhang, Kefan (VerfasserIn), Qin, Chong (VerfasserIn), Luo, Xiao (VerfasserIn), Ding, Tao (VerfasserIn), Chen, Hongli (VerfasserIn)
Pages:2022 29
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Sprache:eng
Veröffentlicht: 2022
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