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基于广义半马尔科夫过程(GSMP)模拟方法实现点堆中子动力学方程的蒙特卡罗求解。该方法模拟裂变系统内中子数和缓发中子先驱核数目的瞬态演化过程,并计算出任意时刻裂变功率和缓发中子源强等物理量。利用本文提出的方法研究快中子增殖堆(简称“快堆”)和热堆参数下的点堆动力学方程,对反应性的阶跃输入、斜坡输入和振荡输入的点堆中子场瞬态过程进行模拟,并与传统数值算法的计算结果进行比较。该方法不存在数值计算的刚性问题,能方便地对复杂反应性输入过程进行计算,并能充分考虑瞬态过程中反应性变化对中子代时间的影响。
Monte Carlo Method for Solving Point - stack Neutron Dynamics Equation Based on Generalized Semi - Markov Process (GSMP) Simulation. The method simulates the transient evolution of the number of neutrons and the number of delayed neutron precursors in the fission system, and calculates the physical quantities of fission power and delayed-onset neutron source intensity at any time. Using the method proposed in this paper, the kinematic equations of point reactor in fast breeder reactor (“fast reactor”) and hot reactor parameters are studied, and the response of step input, slope input and oscillation input of point stack neutron Field transient process is simulated and compared with the traditional numerical algorithm. This method does not have the numerical problem of rigidity, and can easily calculate the complex reactive input process, and can fully consider the influence of the reactivity change on the neutron generation time in the transient process.