截短型燃料组件堆内贮存临界安全分析

Criticality Safety Analysis of the Truncated Fuel Assembly Stored in Reactor

基于小型压水堆特有的截短型燃料组件,建立乏燃料贮存水池几何模型,分析正常贮存及事故工况下的临界安全。选取合理的保守假设,建立适当的计算模型,分别计算了一区和二区正常贮存工况、地震事故工况、组件跌落事故工况、新组件误插入事故工况的反应性。计算得到事故工况下有效增值因子最大值为0.932 83。小型压水堆乏燃料贮存水池临界安全分析中,正常工况及事故工况下计算结果均小于0.95。该设计模型可确保燃料堆内贮存区域处于次临界状态,且安全可控。

Nowadays, for its outstanding performance on safety features and multiple applications, small PWR has gained much attention in the field of nuclear energy. The geometry model of spent fuel storage pool was es- tablished based on truncated fuel assembly which is special used in small PWR. We analyzed the spent fuel pool criticality safety in normal condition and assumed accident condition included earthquake accident, the as- sembly drop accident and assembly error insertion accident with reasonable assumptions. Calculation results show that both in normal condition and assumed accident condition, the maximum value of keff is 0. 932 83 which is less than 0.95 in a suberitieal state. The model can ensure spent pool safety and controllable.