池式研究堆自然循环能力试验及数值模拟

自然循环能力是表征反应堆固有安全性能的重要参数，为了分析某池式研究堆非能动安全性，判断自然循环运行工况载热能力，针对堆芯结构特征开发了自然循环能力分析程序，完成了燃料元件出入口水温实测等验证试验。分析结果表明，堆芯自然循环流量计算结果与试验值符合良好，相对偏差小于1.6%；反应堆自然循环能力随堆池水温度升高而降低，当池水温度为40 ℃时，反应堆自然循环能力为710 kW，表明反应堆具有良好的非能动安全性。

Natural Circulation Capacity Experiment and Numerical Simulation for Pool-Type Research Reactor

The natural circulation capacity is the important parameter that characterizes the safety capability of a nuclear reactor. In order to analysis the passive safety of a pool-type research reactor, and determine the extreme levels of heat-carrying capacity under natural circulation condition, according to the special core structure, a method was proposed to carry out natural circulation experiment, and a software was developed to analysis the natural circulation capability. The calculation results of core flow satisfy experimental values well, and the relative deviation is less than 1.6%. Under the condition the pool water temperature is 40 ℃, the natural circulation capacity of the reactor is no less than 710 kW according to the calculation result of the code. It indicates that this pool reactor has good passive safety ability.