“华龙一号”核电机组硼稀释事故PCI瞬态研究

The Investigation of PCI Transients of Boron Dilution Accident in HPR1000 NPP

基于一维核热耦合程序POPLAR对硼瞬态模块开展了反应性验证,验证结果表明程序对于硼稀释过程的核反馈计算准确性较好。在此基础上采用一维核热耦合方法对硼稀释PCI瞬态过程进行了分析。分析中考虑了堆芯初始状态、R棒棒位及超温ΔT保护信号的影响。计算结果表明,在不考虑保护信号的情况下,初始ΔI越负,R棒提出步越大,堆芯的功率畸变程度及线功率密度峰值愈高;若考虑保护信号,则堆芯初始状态对停堆时刻堆芯功率畸变程度及线功率密度峰值影响较小。

Based on the one-dimensional nuclear and thermal hydraulic coupled code POPLAR,the boron transient analysis model was tested and proved having high accuracy in nuclear feedback prediction.The boron dilution transients were studied using this model.The influence of core initial state,' step and overpower ΔT trip signal of temperature regulation rods were analyzed.The results show that,without consideration of ΔT trip signal,the more negative ΔI is and the less steps regulation rods insert,the worse the power distribution distortion and linear power density are.Nevertheless,the influence of these parameters is little when ΔT trip signal considered.