An accurate solution of point kinetics equations of one-group delayed neutrons and an extraneous neutron source for step reactivity insertion  

作　　者：LI HaoFeng SHANG XueLi CHEN WenZhen 

机构地区：[1]Department of Nuclear Energy Science and Engineering, Naval University of Engineering, Wuhan 430033, China

出　　处：《Chinese Science Bulletin》2010年第36期4116-4119,共4页

基　　金：supported by the National Natural Science Foundation of China (10575131)

摘　　要：The continuous indication of the neutron density and its rate of change are important for the safe startup and operation of reactors. The best way to achieve this is to obtain analytical solutions of the neutron kinetics equations because none of the developed numerical methods can well satisfy the need for real-time or even super-time computation for the safe startup and operation of reactors in practice. In this paper, an accurate analytical solution of point kinetics equations with one-group delayed neutrons and an extraneous neutron source is proposed to calculate the change in neutron density, where the whole process from the subcritical stage to critical and supercritical stages is considered for step reactivity insertions. The accurate analytical solution can also be used as a benchmark of all numerical methods employed to solve stiff neutron kinetics equations.The continuous indication of the neutron density and its rate of change are important for the safe startup and operation of reactors. The best way to achieve this is to obtain analytical solutions of the neutron kinetics equations because none of the developed numerical methods can well satisfy the need for real-time or even super-time computation for the safe startup and operation of reactors in practice. In this paper, an accurate analytical solution of point kinetics equations with one-group delayed neutrons and an extraneous neutron source is proposed to calculate the change in neutron density, where the whole process from the subcritical stage to critical and supercritical stages is considered for step reactivity insertions. The accurate analytical solution can also be used as a benchmark of all numerical methods employed to solve stiff neutron kinetics equations.

关 键 词：中子动力学方程 缓发中子 中子源 POINT 反应性 精确解 安全运行 数值方法 

分 类 号：O571.53[理学—粒子物理与原子核物理] TL329.2[理学—物理]