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机译:计算气冷堆核中旁路流量的数值方法的验证
Korea Atomic Energy Research Institute Daedeok-Daero 989-111, Yuseong-gu, Daejeon 305-353, South Korea;
Korea Atomic Energy Research Institute Daedeok-Daero 989-111, Yuseong-gu, Daejeon 305-353, South Korea;
Korea Atomic Energy Research Institute Daedeok-Daero 989-111, Yuseong-gu, Daejeon 305-353, South Korea;
Korea Atomic Energy Research Institute Daedeok-Daero 989-111, Yuseong-gu, Daejeon 305-353, South Korea;
Department of Nuclear Engineering and Radiological Sciences, University of Michigan 2355 Bonisteel Boulevard, Ann Arbor, Michigan, U.S.A.;
Department of Nuclear Engineering and Radiological Sciences, University of Michigan 2355 Bonisteel Boulevard, Ann Arbor, Michigan, U.S.A.;
Department of Nuclear Engineering and Radiological Sciences, University of Michigan 2355 Bonisteel Boulevard, Ann Arbor, Michigan, U.S.A.;
US Nuclear Regulatory Commission Washington D.C., U.S.A.;
HTGR; Bypass Flow; Prismatic Core; GAMMA+; AGREE; Validation;
机译:计算气冷堆核中旁路流量的数值方法的验证
机译:基于两层模块模型的棱柱形极高温气冷核反应堆堆芯旁流和错流的计算流体动力学分析
机译:均匀加热的缩小标准燃料块测试,用于验证棱镜气体冷却反应器的核心热流体分析码
机译:验证棱镜气冷反应器芯中计算旁通流量的数值方法
机译:在代表性的气冷棱柱形反应堆堆芯模型中的颗粒图像测速测量,用于估算旁路流量。
机译:使用4D流MRI验证主动脉弓数值模拟方法
机译:用于计算气体冷却反应堆堆芯中旁路流动的数值方法的验证