The transient analysis of nuclear reactors is an important issue from a safety point of view. The deterministic methods, by considering different approximations, are extensively used to solve the neutron transport equations. Nowadays, by the continuous increase of computational resources, the feasibility of utilization of pure Monte Carlo methodology in the nuclear reactor transient analysis, without using different approximations, is being increased. In the present work, a detailed Dynamic Monte Carlo (DMC) methodology is developed and employed to investigate the transient analysis of source driven nuclear systems. Analytically solvable time and space and time dependent problems are introduced and solved to verify variance reduction tools used in the DMC methodology. Then, the DMC method is utilized to generate time dependent Green's functions for transient analysis of the source-driven systems (SDSs) studied in literature. The equilibrium and post perturbation transient responses of source driven systems are obtained by utilizing the Green's functions generated for those systems. The newly developed novel method is applied to different transient benchmark problems of SDSs. The performance and validity of the proposed method are discussed through qualitative and quantitative comparisons with the results given for the test and benchmark problems.

从安全角度来看，核反应堆的瞬态分析是一个重要的问题。通过考虑不同的逼近性，确定性方法被广泛用于求解中子输运方程。如今，随着计算资源的不断增加，在不使用不同近似值的情况下，在核反应堆瞬态分析中使用纯蒙特卡洛方法的可行性正在增加。在当前的工作中，详细的动态蒙特卡洛（DMC）方法论被开发出来，并用于研究源驱动核系统的瞬态分析。引入并解决了可解析的时间和时空相关问题，以验证DMC方法中使用的方差减少工具。然后，利用DMC方法生成与时间相关的Green' 的功能，用于对文献中研究的源驱动系统（SDS）进行瞬态分析。源驱动系统的平衡和摄动后瞬态响应是通过利用为这些系统生成的格林函数获得的。新开发的新方法适用于SDS的不同瞬态基准问题。通过定性和定量比较，讨论了所提方法的性能和有效性，并给出了测试和基准问题的结果。新开发的新方法适用于SDS的不同瞬态基准问题。通过定性和定量比较，讨论了所提方法的性能和有效性，并给出了测试和基准问题的结果。新开发的新方法适用于SDS的不同瞬态基准问题。通过定性和定量比较，讨论了所提方法的性能和有效性，并给出了测试和基准问题的结果。