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通过在子通道分析程序ＣＯＢＲＡ－ⅢＣ／ＭＩＴ２中引入能够计算高欠热沸腾区空泡份额的Ｂｏｗｒｉｎｇ模型，定量验证了５ＭＷ核供热堆（ＮＨＲ－５）功率运行时高欠热空泡的存在，且额定工况下堆芯平均空泡率为１．０６×１０－２，并研究了这类空泡的产生及其分布特征。以此为基础，在冷却剂系统分析程序ＲＥＴＲＡＮ－０２中补充高欠热沸腾计算模型，对负荷自跟随特性实验和自稳定性实验进行了分析计算，给出了分析结果与实验结果的比较。同时还研究了高欠热空泡的反应性反馈在动态过程中的作用及其特点。
By introducing the Bowring model which can calculate the void fraction in the zone of high underheated boiling in the subchannel analysis program COBRA-ⅢC / MIT2, the existence of high under-heating vacuoles in the operation of 5 MW nuclear reactor (NHR-5) , And the average void ratio of the core under rated conditions is 1.06 × 10-2. The generation and distribution characteristics of these cavities are also studied. Based on this, the calculation model of high underheating boiling was added in the RETRAN-02 analysis program of the coolant system. The self-follow-up and self-stability experiments of load were analyzed and calculated, and the comparison between the analytical and experimental results was given. At the same time, the role and characteristics of reactive feedback of high underheated cavities in dynamic process were also studied.