压水堆中子脉冲计数率计算与弱源启动分析方法

Calculation of PWR Neutron Pulse Count Rate and Analysis Method for Weak Source Area

利用点堆模型推导了弱源反应堆初始中子脉冲计数率的计算公式,探讨了反应堆盲区范围的确定方法。实例应用表明,该方法符合实际状况,对提高物理启动的安全性具有重要使用价值,可以用于反应堆开盖检修、装卸核燃料、燃料元件储存等核活动的临界安全监督之中。

The calculation formula of neutron pulse count rate was deduced for the weak source reactor using the model of point reactor. Method of blind area confirmation was discussed. The application shows that this method is consistent with the reality and useful for the improvement of the safety of physics star-up, which is applicable in the supervision of critical safety of nuclear activities, such as the maintenance and repair of reactor, loading and unloading of nuclear fuel and storage of fuel element.