不同描述的中子源模型对CFETR中子学计算的影响

摘要

在托卡马克实验装置中,D-T聚变反应释放出的14 MeV高能中子,与周围部件接触会引起包层材料活化、热负载过高等一系列问题,因此在包层设计和优化过程中,相关的中子学计算显得尤为重要.为了研究不同描述的中子源模型对中国聚变工程实验堆(China Fusion Engineering Test Reactor,CFETR)中子学计算的影响,使用基于蒙特卡罗方法的MCNP(Monte Carlo N Particle Transport Code)程序来模拟中子输运过程,分别计算点源、均匀体源、基于L、H、A模约束的中子源模型对不同中子学计算的影响.结果表明,不同描述的中子源模型对氚增殖比影响较小,对中子壁负载和功率密度分布影响比较明显.%Background:In Tokamak experiment device, the 14-MeV high-energy neutrons which D-T fusion reaction releases may cause a series of problems such as material activation, high thermal loading and so on when they contact surrounding parts, so the relative neutronics calculation in the process of blanket design and optimization is particularly important.Purpose: This study aims to analyze the effect of point source, uniform source, neutron source based on L-mode, H-mode, A-mode respectively on different neutronics calculation.Methods: Using MCNP (Monte Carlo N Particle Transport Code) program based on the Monte Carlo method the neutron transport process is simulated and the effect of different neutron source models is calculated.Results: Different descriptions of neutron source models have less influence on tritium breeding ratio, but obvious effects on neutron wall loading and power density distribution.Conclusion: Therefore, proper neutron source model should be applied to calculate different neutronics.