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80 积分 2025-11-05 加入
Evaluation of start-up characteristics for heat pipe-cooled nuclear reactor coupled with recuperated open-air brayton cycle using hardware-in-the-loop
3个月前
已关闭
Transient thermal-hydraulic analysis for fuel assembly blockage accident by cou-pling CFD code with the neutron kinetics model
4个月前
已关闭
Performance of (U,Zr)C-graphite (composite) and of (U,Zr)C (carbide) fuel elements in the Nuclear Furnace 1 test reactor
10个月前
已完结
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