三维多群中子输运蒙特卡罗程序MCMG-Ⅱ基准检验

3-D Monte-Carlo Neutron Transport Code MCMG-Ⅱ and Benchmark Tests

三维多群P3中子输运蒙特卡罗程序MCMG通过版本更新和功能扩充，能够配备各种多群微观、宏观截面库，截面输入文件进一步简化，版本从Ⅰ发展到Ⅱ，参数更新到ENDF／B-Ⅶ库。程序发展了针对物质的碰撞机制，具有并行计算功能。对于12个临界基准问题和1个外源问题，MCMG-Ⅱ计算取得了与实验和连续截面MCNP-5程序一致的结果，计算速度较MCNP-5提高了3～6倍。

The 3-D multigroup P3 neutron transport Monte Carlo code MCMG was developed by adding functions and renewed edition. It can equip various microscopic or macroscopic cross-sections. The cross-section input was simplified. The edition was developed from Ⅰ to Ⅱ. The multigroup cross-section was produced by ENDF/B-Ⅶ library. The collision mechanism about the material was used and the developed MCMG-Ⅱ code has the parallel computational function. Twelve critical benchmarks and an external source problem were calculated, and the almost same results with experb ments and point-wise cross-section MCNP 5 code were obtained. The speedup of MC- MG-Ⅱ is a factor of 3-6 relative to the MCNP 5 in speed.