[1] 反应堆严重事故及安全分析、反应堆仪控及热工水力
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[1] 熔融液柱与冷却剂作用中液柱碎化预测, 原子能科学技术
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- [2] Experimental Research for CHF Sensitivity of Heat Flux Distribution under IVR Conditions, Science and Technolo 2022/03/01
- [3] CAP1400压力容器外壁面临界热通量试验, 上海交通大学学报 2022/01/01
- [4] Performance test of conceptually designed hydraulically suspended passive shut down subassembly for CFR600, Progress in Nuclear 2021/10/01
- [2] Experimental Research for CHF Sensitivity of Heat Flux Distribution under IVR Conditions, Science and Technolo 2022/03/01