Approaches to modeling gas-phase transport in heavy liquid-metal coolant flow in the HYDRA-IBRAE/LM code, which is actual for safety validation of nuclear reactors with a leak in the steam-generator tubes, are examined. A hierarchy of models for determining the dispersed-particle size that are implemented in the code for bubble flow is presented: empirical correlation, transport equation for the density of the interfacial surface area, and kinetic equation for the particle-size distribution function. The results of test calculations are presented.

中文翻译：

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HYDRA-IBRAE / LM热工代码对重液-金属冷却剂流中气相输送的建模

检验了在HYDRA-IBRAE / LM代码中对重金属液体冷却剂流中的气相传输进行建模的方法，该方法对于验证蒸汽发生器管中有泄漏的核反应堆的安全性是实际的。给出了气泡流动代码中实现的用于确定分散粒径的模型层次：经验相关性，界面表面积密度的传输方程和粒径分布函数的动力学方程。给出了测试计算的结果。