核电模拟机中子截面预处理程序的开发与应用  

Development and Application of Neutron Cross Section Pre-procedure in Nuclear Power Simulator

作　　者：刘泰丽 吴帆 单业余 王江 

机构地区：[1]中广核(北京)仿真技术有限公司,北京100094

出　　处：《计算机仿真》2013年第5期121-124,共4页Computer Simulation

摘　　要：堆芯物理系统仿真是核电厂全范围模拟机仿真的核心,数据量庞大、运算程序复杂是其存在的突出问题。阐述了独立于堆芯物理仿真程序的中子截面预处理程序的开发与应用过程,从应用于模拟机的核程序包计算结果入手,综合考虑燃料温度、慢化剂温度、硼浓度、慢化剂密度以及控制棒棒位等物理参数对中子截面的影响,通过多项式拟合重新构建参数关系表达式,目的是提高计算效率和精度,保证实时数据传递。同时,以某CPR1000机组为例,对中子截面预处理程序处理结果进行分析验证,结果证明此预处理程序能较真实地反映堆内组件参数随各独立变量的变化关系,可广泛应用于核电厂堆芯物理仿真。The reactor core simulation is the center of the nuclear power simulation, the data are large and the calculating procedure is complicated. To improve the calculating efficiency and precision, and insure the real-time data transfer, this paper introduced the developing process of the neutron section pre-procedure which is independent of the reactor core simulation procedure. Based on the nuclear procedure package, we took into account of the influ- ence of fuel temperature, moderate temperature, boron concentration, moderate density and control rod position etc, and rebuilt the relation of polynomial expression. Taking the CPR1000 nuclear plant for example, we analyzed and verified the process result of the neutron cross section pre-procedure. The result proves that the pre-procedure can truly reflect the relationship of the assembly parameters changing with the independent parameters, and the method can be widely used in the reactor core simulation of the nuclear power plant.

关 键 词：核电模拟机 堆芯物理 中子截面 预处理程序 开发与应用 

分 类 号：TM743[电气工程—电力系统及自动化]