This work presents the methodology used to expand the capabilities of the Monte Carlo code OpenMC for the calculation of reactor kinetic parameters: effective delayed neutron fraction β_eff and neutron generation time Λ. The modified code, OpenMC(Time-Dependent) or OpenMC(TD), was then used to calculate the effective delayed neutron fraction by using the prompt method, while the neutron generation time was estimated using the pulsed method, fitting Λ to the decay of the neutron population. OpenMC(TD) is intended to serve as an alternative for the estimation of kinetic parameters when licensed codes are not available. The results obtained are compared to experimental data and MCNP calculated values for 18 benchmark configurations.

这项工作介绍了用于扩展蒙特卡罗程序 OpenMC 计算反应堆动力学参数的能力的方法：有效延迟中子分数β _eff和中子生成时间 Λ。然后使用修改后的代码 OpenMC(Time-Dependent) 或 OpenMC(TD) 使用 prompt 方法计算有效延迟中子分数，同时使用脉冲方法估计中子生成时间，将 Λ 拟合到中子种群。当许可代码不可用时，OpenMC(TD) 旨在作为估计动力学参数的替代方案。将获得的结果与 18 种基准配置的实验数据和 MCNP 计算值进行比较。