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机构地区:[1]中国核动力研究设计院中核核反应堆热工水力技术重点实验室,成都610041 [2]国家能源压水反应堆技术开发(实验)中心,成都610041
出 处:《核动力工程》2012年第4期96-101,共6页Nuclear Power Engineering
基 金:2008年度空泡物理和自然循环重点实验室基金(9140C7101010801)
摘 要:在中低压条件下,对矩形窄缝通道两相流动传热进行试验研究,分析两相流动传热的变化规律,拟合出饱和沸腾传热系数计算关系式,并采用简化的一维分析方法对两相压降进行分析计算。试验结果表明:在相同热平衡含汽率(x)情况下,两相流动压降随系统压力(p)的降低而增大,随系统流量的增大而增大的变化规律;p越低,两相流动压降随x的增加而增大越剧烈;流量越大,两相流动压降随x的增加而增大越剧烈。通过数据回归方法得到汽相湿周长比例因子F并拟合了计算关系式,其计算值与试验值符合得较好。矩形窄缝通道内饱和沸腾平均传热系数受p、质量流量及热流密度的影响较大。Two-phase boiling experiments have been performed in narrow rectangular channel at middle-low pressure. Based on the measured pressure drop and temperature across the test section, the effect of pressure and mass flow rate has been analyzed. Saturated boiling heat transfer was studied. And a new correlation has been developed for saturated boiling heat transfer under middle-low pressure condition. Additionally, based on the predigested one-dimensioned model of two-phase boiling flow, a new correlation has been developed for two-phase flow pressure drop under middle-low pressure condition. Furthermore, F parameter has been defined to expresses proportion of moistening perimeter between steam-phase and wall in this new correlation. The calculation results of new correlation predict well the experimental results. The average saturated boiling heat transfer coefficient is great impacted by system pressure, mass flow and heat flux.
关 键 词:中低压 矩形窄缝通道 两相压降 饱和沸腾传热 试验研究
分 类 号:TL33[核科学技术—核技术及应用]
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