秦山第二核电厂辐照燃料组件替代中子源的可行性分析

Possibility Analysis of Substituting Used Fuel Assembly for Neutron Source of Qinshan NPP-2

  • 摘要: 反应堆中子源的作用是提高次临界状态下堆芯的注量水平。在实际运行中,可能发生停堆时间较长致使中子源衰减,或中子源发生破损无法继续使用的情况。本文通过对已辐照燃料组件自发中子源和源量程探测器响应的计算分析,探讨使用已辐照燃料组件替代中子源的可能性。计算结果表明,首组入堆组件燃耗在24 100 MW•d•tU-1以上即可满足中子计数率监测的要求。本方法可为中子源意外破损提供解决方案。

     

    Abstract: The neutron source is used to increase the neutron fluence of reactor in subcritical condition. In the actual operation, either neutron source decay caused by long-time shutdown or neutron source damage could make further use impossible. By calculating and analyzing spontaneous neutron source of used fuel assembly and source range detector response, the possibility of substituting used fuel assembly for neutron source was discussed. According to the result, the requirement of neutron count rate monitoring can be satisfied on condition that the first loading fuel assembly has a burnup of more than 24 100 MW•d•tU-1. This method can provide a solution to unexpected neutron source damage.

     

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