核电厂核仪表系统功率量程中子注量率变化率校正系数的仿真研究  

Simulation Study on Correction Factor for Changing of Power Range Neutron Flux Rate of NPP Nuclear Instrumentation System

作　　者：张英[1] 陈智[1] 王殳[1] 孙剑[1] 

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,成都610041

出　　处：《核动力工程》2012年第6期42-45,60,共5页Nuclear Power Engineering

摘　　要：核电厂核仪表系统功率量程中子注量率变化率是重要的保护参数,对该参数的计算进行正确的校正,既可以保证在发生弹棒和落棒事故时正常执行停堆功能,又可以在寿期初和寿期末发生甩负荷至厂用电运行工况时避免停堆而影响核电厂的经济性。依据功率量程中子注量率变化率校正的基本原理,以岭澳核电站二期和秦山核电厂二期扩建工程为例,论述了利用仿真分析工具,开展中子注量率变化率校正系数仿真研究的基本方法,相关研究结果已成功应用于现场调试。The change rate of neutron flux in nuclear power plant （NPP） nuclear instrumentation system is an important protection parameter. If the parameter is corrected properly, the reactor trip function not only can be carried out normally in rod ejection accident and rod drop accident, but also the economic effect can be assured by avoiding reactor trip at the houseload rejection operation condition. The basic correction theory is explained in this paper. Furthermore, the paper uses the Ling＇ao phase II NPP project and Qinshan phase II NPP extension project as examples and discusses the basic simulation study method of correction factor for the change rate of the neutron flux by the simulation analysis tools. The study result is applied successfully in tests on site.

关 键 词：核仪表系统 中子注量率变化率 校正 仿真研究 

分 类 号：TL36[核科学技术—核技术及应用]