核燃料组件运输容器的临界安全分析

Criticality Safety Analysis of Nuclear Fuel Assembly Transport Container

为验证CEFR-MOX燃料组件运输容器临界安全分析结果,本文对临界安全计算模型、正常和事故工况下情景假设、临界安全分析等内容使用MCNP程序进行了分析与计算.校核结果表明:正常和事故工况下,CEFR-MOX燃料组件运输容器Kef值变化趋势与原设计基本吻合,最大Kef值与原设计Kef值相对偏差不超过1%。

In order to verify the criticality safety analysis results of CEFR-MOX fuel assembly transport container,this paper conducts independent check analysis and calculation for the criticality safety calculation model,scenario assumptions under normal and accident condition,and criticality safety analysis.The results of the check indicate that the change trend of the Keff value is basically consistent with the original design under normal and accident conditions.The relative deviation between the maximum Keff value and the original design Keff value does not exceed 1%.