一种采用主回路精确流量校准核仪表系统方法的研究

Study on one Method for Accurate Primary Loop Flow Calibration of Nuclear Instrumentation System

核电厂核仪表系统功率量程中子注量率变化率是反应堆保护系统的重要参数,对该参数的计算校准,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。当前核电厂,核仪表系统功率量程中子注量率变化率引入的主回路平均温度信号和主泵转速信号进行校准。本文着重介绍一种采用精确的反应堆冷却剂系统主回路流量来校准中子注量率变化率的方法,对其进行研究与探讨,以达到提高功率量程中子注量率变化率的校准精度的目的。

The change rate of neutron flux in nuclear power plant （NPP）nuclear instrumentation system is an important protection parameter. Calibration of the parameter can ensure the normal reactor shutdown function when rod drop and rod eject accident occurred, and can avoid affect the economy of NPP via reactor trip on the condition of load shedding on the beginning and the ending of the life time. In current NPP, the change rate of neutron flux is calibrated according to the primary loop average temperature signals and reactor coolant pump speed signals. This article highlights one change rate of neutron flux calibration method according to the accurate primary loop flow of reactor coolant system, so as to improve the calibration accuracy of the change rate of neutron flux.