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正在成为反应堆物理设计的重要手段。同时，随着对安全性的要求不断提高，敏感性和不确定度分析成为反应堆物理的研究热点。本项目拟以我们研究团队自主研发成功的已具备堆分析用基本功能（包含临界与燃耗计算、固定源计算、源收敛加速、在线截面处理、复杂几何处理、高效并行、核热耦合、动态模拟等）的蒙卡程序RMC为依托，研究基于连续能量蒙卡计算的敏感性和不确定性分析的方法，包括：有效增值因子对核截面、几何尺寸和材料密度等系统特征参数的敏感性分析方法；广义微扰法应用于其它系统响应的不确定性分析方法；蒙卡燃耗计算中的误差传递机理及不确定度分析等。最终，开发具备完善的敏感性和不确定度分析功能的自主堆用蒙卡程序RMC，为具有不同复杂几何与能谱的新一代或新概念反应堆的堆芯及安全性分析与设计提供工具和手段。

Owing to the need of modeling geometrically and spectrum complex systems with improved fidelity and the development of computers technology, the continuous energy Monte Carlo method is becoming an important alternative method for reactor design and analysis. And as the demand for nuclear safety becomes higher and higher, the sensitivity and uncertainty analysis cause more and more attention in the field of reactor physics. This study will be done on the basis of Reactor Monte Carlo code RMC, developed by ourselves, REAL group of Tsinghua University, which can be applied in criticality, burnup, source convergence acceleration, on-the-fly cross sections processing, high efficiency Geometry processing , large-scale parallel, N-TH coupling, kinetics, etc. We are going to study the sensitivity and uncertainty analysis method in the continuous energy Monte Carlo calculation including the methods to calculate effective multiplication factor sensitivity coefficient to the nuclear cross sections , system dimensions, number densities, etc; the implement of generalized perturbation method to calculate uncertainty of other system responses in the continuous energy Monte Carlo criticality calculation; the uncertainty propagation analysis method in the Monte Carlo burnup calculation. Finally, we will implement this methods in RMC code to make it capable for sensitivity and uncertainty analysis, which will be provided as a tool for the reactor core safety analysis for the geometrically and spectrum complex systems and the next generation reactors.