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在CYBER 825计算机上移植了引进的反应堆燃料组件计算程序系统MARIA以后,又将该程序系统推广应用于加浓铀裸球临界装置。为了考虑共振裂变与共振吸收对计算结果的影响,研制了MARIA辅助程序MA。根据美国评价核数据库ENDF/B-IV的数据,利用MA程序对MARIA程序系统中的多群常数库进行了修正,部分数据文档作了更新。反应堆的几何曲率和增殖因子在输出通道中给出。计算结果的精度可以与Monte Carlo和Sn方法相比较。它与实验结果比较,在1％以内是符合的。
After the introduction of MARIA, an embedded reactor fuel assembly calculation system, on the CYBER 825 computer, the program system was extended to the uranium-enriched critical ballistic unit. In order to consider the influence of resonance fission and resonance absorption on the calculation results, MARIA auxiliary program MA was developed. Based on the data of the US evaluation of the nuclear database ENDF / B-IV, the MA program was used to revise a large number of constant libraries in the MARIA program system and some of the data files were updated. Reactor geometry curvature and propagation factors are given in the output channel. The accuracy of the calculated results can be compared with the Monte Carlo and Sn methods. It is in line with the experimental results, within 1% is consistent.