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Investigation of subcooled flow boiling model under low pressure

机译:低压过冷流沸腾模型研究

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Two fluid model integrating a set of closure relationships (such as inter-phase heat transfer model, inter-phase mass transfer model, inter-phase momentum transfer model, mean bubble diameter model, bubble departure diameter model, bubble departure frequency model, onset of nucleate boiling model, wall heat flux partition model) are applied to solve the local flow and heat transfer of subcooled flow boiling under low pressure, and local flow parameters such as volume fraction, liquid velocity, vapor phase etc. are obtained using developed code. The subcooled flow boiling results predicted in this paper are compared to the subcooled flow boiling experimental results of TH Lee~([1]) etc.in annular channel with inner tube heated uniformly and adiabatic outer tube, and they agree well. The code can also be used to predict the multiphase flow field in power reactor core when the subcooled flow boiling take place and the critical heat flux of Departure Nucleate Boiling(DNB) in reactor core and it is meaningful for reactor core design.
机译:集成了一组封闭关系的两种流体模型(如相间传热模型,相间传质模型,相间动量传递模型,平均气泡直径模型,气泡离开直径模型,气泡离开频率模型,应用核沸腾模型,壁热通量分配模型)求解低压下过冷沸腾的局部流动和传热,并利用已开发的代码获得了局部流动参数,例如体积分数,液体速度,气相等。将本文预测的过冷流沸腾结果与TH Lee〜([1])等在内管均匀加热的绝热环形通道和绝热外管中的过冷流沸腾实验结果进行了比较,两者吻合得很好。该代码还可用于预测发生过冷流动沸腾时反应堆堆芯中的多相流场以及反应堆堆芯中离析核沸腾(DNB)的临界热通量,这对于反应堆堆芯设计具有重要意义。

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