【作者】 段新会；

【导师】 佟振声；

【作者基本信息】 华北电力大学 ， 热能工程， 2001， 硕士

【摘要】 本文对压水堆堆芯及其控制系统进行了建模与仿真研究。堆芯中子通量分布采用分离变量法对两群六缓发中子组三维扩散方程来实时求解，并考虑慢化剂密度、硼浓度、氙和钐中毒、控制棒位置、燃料和慢化剂温度、燃料燃耗等因素对中子通量分布的影响。在对先进的反应堆控制模式—G模式进行仿真分析的基础上，设计出用于负荷跟踪过程的硼浓度三维模糊控制系统。利用C++和Fortran混合编程技术开发了实时仿真与调试软件，对堆芯仿真模型及其控制系统仿真模型进行实时运算均取得满意结果，本文所作研究对建立全范围核电站模拟机具有一定的分析指导意义。更多还原

【Abstract】 The author studied on the modeling and simulation of PWR core and itscontrol systems. The neutron flux distributions are calculated from the 3Ddiffosion equations of two energy groups and six delayed neutron precursors byseparaing the "time" and "space" variables. The following parameters are takenaccount of the effects on reactivity’ moderator density boron concentration,xenon and samarium poisoning, control rod positions, moderator and fueltemperature, fuel bum-uP and so on. Basing on the analysis of the mode G, a 3dimension fuzzy control system of boron concentration is designed for loadfollowing. Using the mixed-language programming with C++ and Fortran, thereal-time simulation software is developed. The results of the core model and itscontrol system model are satisfatory. This paPer is helpful to analyze and directfor the full scope simulator of nuclear power station.Duan Xinhui (Thermal Power Engineering)Directed by Pro f Tong Zhensheng更多还原