混合能源堆多群中子参数库研制

Development of Multi-Group Library for Fusion-Fission Hybrid Reactors

根据聚变-裂变混合能源装置计算的需求,利用微观评价核数据库ENDF/B-VI.8,研制了包括100多个核素的187群中子参数,用于中子输运方程的计算。通过选取合适的能群结构和权重谱,并考虑温度、热散射以及共振自屏效应等的影响,建立并拓展了适合混合堆研究需要的多群参数库。为了检验参数库中数据的适用性,采用一维中子和光子输运程序ANISN对一组基准装置进行了临界计算。结果表明参数库可用于混合能源堆设计计算。

According to the calculation requirement of fusion-fission hybrid reactors and the relevant studies,a new 187-group constants library has been developed.This library containing more than 100 nuclides with basic data selected from ENDF/B-VI.8 can be used to calculate the neutron transport equation.The weight flux,group structures,thermal neutron transport and the Bondarenko option is considered during the process.Some calculations and comparative analyses are performed based on a series of existing benchmark experiments using ANISN.The result indicates that the library satisfies the basic requirements on calculation for designing the hybrid energy reactors.