摘要
本文为200MW核供热堆建立了一个用于大功率运行范围控制系统仿真的非线性动态模型。模型除了采用点中子动态方程、集中参数的慢化剂温度和燃料温度负反馈等压水堆控制系统常用的建模方法之外,为了使模型适用于大功率运行范围,还重点考虑了主回路自然循环对堆芯内冷却剂和燃料棒之间的传热系数、主换热器换热系数、主回路时间常数的影响,以及二回路流量变化引入的非线性。仿真结果表明,模型具有较高的精度,可用于控制系统仿真。
In this paper the author gives a nonlinear dynamic model of 200MW nuclear heating reactor for control system simulation in a wide power range.Besides the point neutron kinetic formulation and the lumped coolant temperature and fuel temperature feedback which are the usual modeling methods for PWR,the natural circulation of primary loop,which affects diathermanous coefficient between the coolant and the fuel,the heat exchange coefficient of the primary heat exchanger and the time constant of primary loop,are considered in focus.The secondary flow rate variation inserting the nonlinear properties is also considered during modeling.The simulation results shows that the model is accuracy enough to be used for control system simulation.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
1998年第4期312-319,共8页
Nuclear Power Engineering
关键词
核供热堆
非线性动态模型
控制系统仿真
MW Nuclear heating reactor Nonlinear dynamic model Control system simulation Natural circulation