机译:不同于核沸腾相关的SPERT-IV实验的PARET-ANL建模
Institute of Nuclear Technology and Radiation Protection National Centre for Scientific Research "Demokritos," 15130 Aghia Paraskevi Athens, Greece;
Institute of Nuclear Technology and Radiation Protection National Centre for Scientific Research "Demokritos," 15130 Aghia Paraskevi Athens, Greece;
McMaster University, Department of Engineering Physics 1280 Main Street West, Hamilton, Ontario, Canada;
De: hydraulic diameter (m); G: mass velocity; Hf: enthalpy of saturated liquid (kJ/kg); Hfg: heat of evaporation (kJ/kg); Hin: inlet enthalpy (kJ/kg);
机译:核沸腾研究的沸腾沸腾流动的计算流体动力学模型
机译:预测核池沸腾过程中光滑平面上气泡离开半径的相关性
机译:泡沫池沸腾泡沫形状与脱落的数值模型
机译:基于沸腾水流高速视频的核沸腾临界热通量预测近壁界面面积模型
机译:对偏离核沸腾的理论预测的改进。
机译:具有不同润湿表面的纳米/微结构上的核沸腾性能
机译:讨论:“影响垂直圆管流动的蒸汽水混合物中核沸腾因素的实证相关性”(Pasint,D.和Pai,R. H.,1966,Asme J.传热,88,PP。367-373)
机译:通过Weisman基于物理的DNB(离开核沸腾)相关性计算的环形流动通道中的核沸腾的偏离。