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机译:OPR-1000双冷环形核燃料的热工水力性能评估
LWR Fuel Development Division, Korea Atomic Energy Research Institute, 989-171 Daedeok-Daero, Yuseong-Gu, Daejeon 305-353, Republic of Korea;
LWR Fuel Development Division, Korea Atomic Energy Research Institute, 989-171 Daedeok-Daero, Yuseong-Gu, Daejeon 305-353, Republic of Korea;
LWR Fuel Development Division, Korea Atomic Energy Research Institute, 989-171 Daedeok-Daero, Yuseong-Gu, Daejeon 305-353, Republic of Korea;
LWR Fuel Development Division, Korea Atomic Energy Research Institute, 989-171 Daedeok-Daero, Yuseong-Gu, Daejeon 305-353, Republic of Korea;
机译:基于K-omega SST湍流模型的双冷却环形燃料VVER-1000核反应堆热工水力分析
机译:双冷却环形燃料对VVER-1000核反应堆热功率提升率的影响研究
机译:双冷却环形核燃料下端塞中侧孔的压力损失系数和流量
机译:OPR1000应用的双冷却环形燃料的热力和热力学评估
机译:乏核燃料废料包装上热喷涂涂层的热应力分析
机译:导热和机械稳健的石墨烯纳米片增强UO2复合核燃料
机译:乏燃料核电项目的热工水力可行性评估
机译:乏核燃料项目的热工水力可行性评估