AP1000乏燃料贮存格架临界安全分析

Criticality Safety Analysis for AP1000 Spent Fuel Storage Racks

  • 摘要: 基于SCALE6程序包对西屋公司采用燃耗信任制技术的AP1000核电厂乏燃料贮存格架(SFSRs)临界安全分析过程进行了复现,在此基础上结合AP1000核电厂堆芯反应性控制特性,分析了轴向燃耗分布对系统反应性的影响。结果表明,高燃耗下采用机械补偿(MSHIM)轴向燃耗分布计算得到的系统反应性更保守,同时临界安全分析中需考虑吸收体在组件燃耗过程中对反应性的影响,且不应信任可溶硼。

     

    Abstract: Criticality safety analysis for AP1000 spent fuel storage racks (SFSRs) employing burnup credit was recalculated based on SCALE6 code package. Combined with the design characteristics of AP1000 core reactivity control, the effect of axial burnup distribution on system reactivity was analyzed. The results show that the system reactivity is more conservative at high burnup using MSHIM axial burnup distribution, and the effect of neutron absorbers exposure on the reactivity of assembly during depletion should be considered in criticality safety analysis, and soluble boron should not be credited.

     

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