Multiple size group （MUSIG） model combined with a threedimensional twofluid model were em ployed to predict subcooled boiling flow of liquid nitrogen in a vertical upward tube. Based on the mechanism of boiling heat...Multiple size group （MUSIG） model combined with a threedimensional twofluid model were em ployed to predict subcooled boiling flow of liquid nitrogen in a vertical upward tube. Based on the mechanism of boiling heat transfer, some important bubble model parameters were amended to be applicable to the modeling of liquid nitrogen. The distribution of different discrete bubble classes was demonstrated numerically and the distribu tion patterns of void fraction in the wallheated tube were analyzed. It was found that the average void fraction in creases nonlinearly along the axial direction with wall heat flux and it decreases with inlet mass flow rate and sub cooled temperature. The local void fraction exhibited a Ushape distribution in the radial direction. The partition of the wall heat flux along the tube was obtained. The results showed that heat flux consumed on evaporation is the leading part of surface heat transfer at the rear region of subcooled boiling. The turning point in the pressure drop curve reflects the instability of bubbly flow. Good agreement was achieved on the local heat transfer coefficient aalnst experimental measurements, which demonstrated the accuracy of the numerical model.展开更多
Research reactors with neutron fluxes higher than 10^(14) n cm^(−2) s^(−1) are widely used in nuclear fuel and material irradiation,neutron-based scientific research,and medical and industrial isotope production.Such ...Research reactors with neutron fluxes higher than 10^(14) n cm^(−2) s^(−1) are widely used in nuclear fuel and material irradiation,neutron-based scientific research,and medical and industrial isotope production.Such high flux research reactors are not only important scientific research facilities for the development of nuclear energy but also represent the national comprehensive technical capability.China has several high flux research reactors that do not satisfy the requirements of nuclear energy development.A high flux research reactor has the following features:a compact core arrangement,high power density,plate-type fuel elements,a short refueling cycle,and high coolant velocity in the core.These characteristics make it difficult to simultaneously realize high neutron flux and optimal safety margin.A new multi-mission high flux research reactor was designed by the Institute of Nuclear and New Energy Technology at Tsinghua University in China;the reactor can simul-taneously realize an average neutron flux higher than 2.0×10^(15) n cm^(−2) s^(−1) and fulfill the current safety criterion.This high flux research reactor features advanced design concepts and has sufficient safety margins according to the preliminary safety analysis.Based on the analysis of the station blackout accident,loss of coolant accident,and reactivity accident of a single-control drum rotating out accidently,the maximum temperature of the cladding surface,minimum departure from nucleate boiling ratio,and temperature difference to the onset of nucleate boiling temperature satisfy the design limits.展开更多
在低质量流率条件下,对垂直上升内螺纹管在亚临界和近临界压力区的传热特性进行了实验研究。实验参数范围为压力p=12-22.5 MPa,质量流率G=170-420 kg/（m^2·s）,内壁热负荷q=150-366 k W/m^2。实验结果表明：在亚临界压力区,垂直...在低质量流率条件下,对垂直上升内螺纹管在亚临界和近临界压力区的传热特性进行了实验研究。实验参数范围为压力p=12-22.5 MPa,质量流率G=170-420 kg/（m^2·s）,内壁热负荷q=150-366 k W/m^2。实验结果表明：在亚临界压力区,垂直上升内螺纹管发生了第二类传热恶化,即干涸（dryout）。内壁热负荷和压力的增大,均会导致干涸点的提前以及干涸后内壁温度的峰值增大。质量流率对干涸点的影响呈现非单调性,存在一界限质量流率。当质量流率小于界限质量流率时,干涸点随质量流率的增加而提前;当质量流率大于界限质量流率时,干涸点随质量流率的增加而推迟。在近临界压力区的亚临界压力部分,内壁热负荷较高时容易发生第一类传热恶化,即膜态沸腾（DNB）。内壁热负荷的增大和质量流率的减小,均会导致传热恶化的提前以及膜态沸腾后的温度飞升值增加。在近临界压力区的超临界压力部分,内螺纹管传热良好,在拟临界区域出现一定程度的传热强化,其传热特性和亚临界压力区的传热特性相似。展开更多
针对0.15、0.2、0.3 MPa 3个压力进行乙烷池内核态沸腾可视化实验研究,实验测量的热通量范围是14.27~81.22 k W·m^(-2)。高速摄像机采集得到竖直铜棒的光滑上表面的乙烷气泡的脱离图像,利用图像处理软件获得气泡脱离直径,并分析了J...针对0.15、0.2、0.3 MPa 3个压力进行乙烷池内核态沸腾可视化实验研究,实验测量的热通量范围是14.27~81.22 k W·m^(-2)。高速摄像机采集得到竖直铜棒的光滑上表面的乙烷气泡的脱离图像,利用图像处理软件获得气泡脱离直径,并分析了Jacob数(Ja)与气泡脱离直径的变化关系。实验所测直径与引用广泛的6个关联式进行比较,Kim和Kim(2006)模型的预测效果较好,绝对平均偏差均在30%以内,但在0.15 MPa工况下,50%的预测值偏差为30%~40%。Kim和Kim(2006)模型提出Bo^(1/2)和Ja呈幂函数的关系。在对比基础上,用乙烷的气泡脱离直径数据拟合得到的新关联式与实验数据偏差在±30%以内。另外,选取文献中甲烷的气泡脱离直径与新关联式进行对比,在4种压力下的预测值偏差几乎均在±30%以内(只有一个预测值在±30%以外)。新关联式对甲烷和乙烷的工况具有良好的预测效果,但是由于拟合数据所用的Ja较小,在使用范围上具有一定的局限性。展开更多
基金Supported by the National Natural Science Foundation of China （51106119, 81100707）, the Fundamental Research Funds for the Central University of China, Doctoral Fund of Ministry of Education （20110201120052） and the National Science and Technology Sur0orting Item （2012BAA08B03）.
文摘Multiple size group （MUSIG） model combined with a threedimensional twofluid model were em ployed to predict subcooled boiling flow of liquid nitrogen in a vertical upward tube. Based on the mechanism of boiling heat transfer, some important bubble model parameters were amended to be applicable to the modeling of liquid nitrogen. The distribution of different discrete bubble classes was demonstrated numerically and the distribu tion patterns of void fraction in the wallheated tube were analyzed. It was found that the average void fraction in creases nonlinearly along the axial direction with wall heat flux and it decreases with inlet mass flow rate and sub cooled temperature. The local void fraction exhibited a Ushape distribution in the radial direction. The partition of the wall heat flux along the tube was obtained. The results showed that heat flux consumed on evaporation is the leading part of surface heat transfer at the rear region of subcooled boiling. The turning point in the pressure drop curve reflects the instability of bubbly flow. Good agreement was achieved on the local heat transfer coefficient aalnst experimental measurements, which demonstrated the accuracy of the numerical model.
文摘Research reactors with neutron fluxes higher than 10^(14) n cm^(−2) s^(−1) are widely used in nuclear fuel and material irradiation,neutron-based scientific research,and medical and industrial isotope production.Such high flux research reactors are not only important scientific research facilities for the development of nuclear energy but also represent the national comprehensive technical capability.China has several high flux research reactors that do not satisfy the requirements of nuclear energy development.A high flux research reactor has the following features:a compact core arrangement,high power density,plate-type fuel elements,a short refueling cycle,and high coolant velocity in the core.These characteristics make it difficult to simultaneously realize high neutron flux and optimal safety margin.A new multi-mission high flux research reactor was designed by the Institute of Nuclear and New Energy Technology at Tsinghua University in China;the reactor can simul-taneously realize an average neutron flux higher than 2.0×10^(15) n cm^(−2) s^(−1) and fulfill the current safety criterion.This high flux research reactor features advanced design concepts and has sufficient safety margins according to the preliminary safety analysis.Based on the analysis of the station blackout accident,loss of coolant accident,and reactivity accident of a single-control drum rotating out accidently,the maximum temperature of the cladding surface,minimum departure from nucleate boiling ratio,and temperature difference to the onset of nucleate boiling temperature satisfy the design limits.
文摘在低质量流率条件下,对垂直上升内螺纹管在亚临界和近临界压力区的传热特性进行了实验研究。实验参数范围为压力p=12-22.5 MPa,质量流率G=170-420 kg/（m^2·s）,内壁热负荷q=150-366 k W/m^2。实验结果表明：在亚临界压力区,垂直上升内螺纹管发生了第二类传热恶化,即干涸（dryout）。内壁热负荷和压力的增大,均会导致干涸点的提前以及干涸后内壁温度的峰值增大。质量流率对干涸点的影响呈现非单调性,存在一界限质量流率。当质量流率小于界限质量流率时,干涸点随质量流率的增加而提前;当质量流率大于界限质量流率时,干涸点随质量流率的增加而推迟。在近临界压力区的亚临界压力部分,内壁热负荷较高时容易发生第一类传热恶化,即膜态沸腾（DNB）。内壁热负荷的增大和质量流率的减小,均会导致传热恶化的提前以及膜态沸腾后的温度飞升值增加。在近临界压力区的超临界压力部分,内螺纹管传热良好,在拟临界区域出现一定程度的传热强化,其传热特性和亚临界压力区的传热特性相似。
