neutron kinetics

Exponential Function Method for Solving Point Reactor Neutron Kinetics Equations

点堆中子动力学方程的指数基函数法求解

When the great reactivity reactor is introduced, the point reactor neutron kinetics equation is solved with uncoupling method, and the new reactor power expression is derived.

当引入大阶跃反应性时，应用去耦合法求解中子动力学方程，导出了堆功率新的响应表达式。

A sort of non-parameter model is constructed with the unit step response of the nuclear reactor neutron kinetics system. Furthermore, a sort of constant neutron flux density control law is presented using a predictive control algorithm.

利用核电站反应堆中子动力学系统的单位阶跃响应数据，获得了该系统的非参数模型，且提出了一种中子注量率恒值问题的预测控制方法。

High-Order End Floating Method ── for Solving Point Reactor Neutron Kinetics Equations

高次端点浮动法&解点堆中子动力学方程

The point reactor neutron kinetics equations are stiff differential equations. A pithy efficient method for overcoming the stiffness of the point reactor neutron kinetics equations, the floating end method is presented in this paper.

点堆中子动力学方程是一个刚性微分方程，本文提出一个简洁有效地克服点堆中子动力学方程刚性的方法&端点浮动法。

A New Method for Overcoming the Stiffness of the Point Reactor Neutron Kinetics Equations& the Floating End Method

克服点堆中子动力学方程刚性的新方法&端点浮动法

A new numerical method of solving the point reactor neutron kinetics equations

一个新的求解点堆中子动力学方程组的数值方法

Solution of Point Reactor Neutron Kinetics Equation Using Precise Time Integration Algorithm

反应堆时空动力学方程的解法研究应用精细时程积分法求解点堆中子动力学方程组