反应堆中子动力学方程仿真算法及其应用

Simulation Method for Nuclear Power System and Application

介绍了一种适合于求解反应堆中子动力学方程的刚性限制法。该方法的主要特点是引入一个辅助函数ｗ（ｔ）而将刚性分离，使其仅在解发中子方程中存在刚性，而该方程可解析积分，因此，中子动力学方程的求解步长可取得较大。文中给出了几种反应性扰动下，采用该方法的计算结果与精确解的比较。并将该法用于秦山二期核电站反应堆功率控制系统的瞬态计算，结果令人满意。５６０秒瞬态过程，在ＨＰ－２８６微机上的计算耗时仅８０秒左右，说明在微机上可实现核动力装置的实时甚至超实时仿真。

The stiffness confinement method (SCM) for solving the reactor neutron kinetic equations is described. The main characteristic of the method is to define an auxiliary function w(t) to decouple the stiffness from the differential equations for precursors and confine it to the prompt neutronics equation which can be analytically solved. As a result, the time step increment can be greatly increased and much computing time can be saved, as compared to other conventional methods. The results compared against the exact ones are given under several reactivity disturbance transients. The method is used in the nuclear steam supply system (NSSS) transient calculation of Qinshan phase Ⅱ nuclear power plant. The results are satisfactory. It is occupied only about 80s for a 560s process of Qinshan phase Ⅱ nuclear reactor power control system simulation. It makes it possible to accomplish NSSS real-time even fast-time simulation in a microcomputer.