中子动态参数的准确分析与反应堆的安全特性紧密相关.固态燃料钍基熔盐实验堆(Thorium-based Molten Salt experiment Reactor with Solid Fuel, TMSR-SF1)作为第四代新堆型,采用蒙特卡罗输运程序计算其动态参数更有利于核安全评审.本文基于较通用的蒙特卡罗多粒子输运(Monte Carlo N Particle Transport Code, MCNP)程序,植入了动态参数直接统计方法,用于计算TMSR-SF1中的有效缓发中子份额和有效中子代时间.通过多个ICSBEP (International Criticality Safety Benchmark Evaluation Project)基准题的检验,计算结果与基准题实验误差在±5%以内,证明了该方法的准确性.运用该方法计算得到TMSR-SF1中6组有效缓发中子份额和有效中子代时间随燃耗深度的变化,其计算结果与采用 MCNP 共轭通量方法所得的数据误差在±3%以内,证明该方法用于TMSR-SF1的动态参数分析是合理可靠的.%[Background] Kinetics parameters play an important role on reactor safety analysis and dynamic behavior. Thorium-based molten salt experiment reactor with solid fuel (TMSR-SF1) is a new kind of reactor. Using Monte Carlo code to calculate kinetics parameters is in favor of its nuclear safety license. [Purpose] This study aims at realizing the direct statistical calculation of kinetics parameters in Monte Carlo code, and applying this method to obtain the effective delayed neutron fraction and effective neutron generation time of TMSR-SF1. [Methods] We implant the direct statistical method into MCNP (Monte Carlo N Particle Transport Code) code by tallying the fission neutron type and fly time, and verify its accuracy with multiple ICSBEP (International Criticality Safety Benchmark Evaluation Project) benchmark. [Results] The benchmark kinetics parameters calculated by direct statistical method are consistent with experiment measured value (±5% deviation). The effective delayed neutron fraction and effective neutron generation time of TMSR-SF1 we obtained, are close to that of conjugate flux method based on MCNP code. [Conclusion] It is reliable to use direct statistical method to calculate kinetics parameters of TMSR-SF1.
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