论文部分内容阅读
为了预测正常功率下快堆单个燃料组件入口瞬间完全堵流所导致的事故序列,根据SCARABEE-N系列实验建立了相关模型。采用两流体模型来描述冷却剂的两相热工水力行为;包壳的流动、燃料的熔化及塌陷采用类似SURFA SS程序的经验性方法处理;对于事故后期形成的UO2-钢混合体热源沸腾池,采用一维半经验模型描述。对SCARABEE BE+1实验进行了计算,计算结果与实验结果基本吻合。在此基础上,对中国实验快堆(CEFR)在此事故工况下的行为进行了预测,结果表明堵流后7.2~8.0 s事故传播到相邻燃料组件。
In order to predict the sequence of accidents caused by complete blockage at the instantaneous inlet of a single fuel assembly at normal power, a correlation model was established according to the SCARABEE-N series of experiments. The two-fluid model was used to describe the thermal-hydraulic behavior of the two phases of the coolant. The flow of the cladding, the melting and collapse of the fuel were treated empirically with similar SURFA SS procedures. For the UO2- , Using one-dimensional semi-empirical model description. The SCARABEE BE + 1 experiment was calculated, and the calculated results are in good agreement with the experimental results. On this basis, the behavior of China Experimental Fast Reactor (CEFR) under this accident condition is predicted, and the results show that the accident of 7.2-8.0 s after the plugging flow is propagated to the adjacent fuel assemblies.