基于研究几何与能谱复杂的反应堆系统的需求以及计算机技术的发展，使用连续能量蒙特卡罗方法成为反应堆物理研究与设计的重要手段。随着设计安全性和经济性要求的不断提高以及需求多样化，针对随机中子场的随机中子动力学研究成为重要研究课题之一。本项目拟以我们自主研发成功的用于反应堆堆芯计算分析（包含临界与燃耗计算、固定源与屏蔽计算、源收敛加速、在线截面处理、高效几何处理、混合并行、核热耦合、中子动力学与瞬态过程分析、敏感性与不确定度计算等）的三维输运蒙卡程序RMC为依托，针对脉冲堆弱源点火实验研究、核燃料加工生产和乏燃料后处理中弱源启动的临界事故分析、反应堆无源启动过程中的盲区阶段监测分析以及反应堆中子噪声分析中涉及的随机中子动力学分析方法展开研究。最终，开发具备随机中子动力学分析功能的自主对用蒙卡程序RMC，为新一代脉冲堆设计、临界安全事故分析、反应堆无源启动和反应堆噪声分析等提供有力的工具和手段。

To meet the demand of accurately modeling the reactor systems with complex geometry and energy spectrum and owing to the development of computer technology, the continuous energy Monte Carlo method is becoming an important alternative method for reactor research and design. And as the safety and economics in design need to be improved with diversified requirements, the stochastic kinetics analysis for stochastic neutron field raises more and more attentions in the field of reactor physics. This study will be based on our own Reactor Monte Carlo code RMC which can be applied in criticality, burnup, fixed source and shielding calculation, source convergence acceleration, on-the-fly cross sections processing, high efficiency geometry processing, hybrid parallelism, N-TH coupling, kinetics, S/U etc. We are planning to study the stochastic neutron kinetics analysis method in the framework of continuous energy Monte Carlo applied to research on and analysis of pulsed reactor experiments initiated by weak neutron source, the criticality accidents in the nuclear fuel processing and spent fuel reprocessing, the monitoring of neutron behavior in the startup stage of reactor by spontaneous neutron source and the neutron noise analysis in the reactor. Finally, we will implement these methods and algorithm in RMC code to make it capable of stochastic neutron kinetics analysis, which will be provided as an efficient tool for pulse reactor design, criticality accident analysis, reactor startup by spontaneous neutron source and neutron noise analysis in reactors.