三维多群P5中子输运蒙特卡罗程序MCMG及检验

摘要

本工作介绍了自主开发研制的三维多群P5中子输运蒙特卡罗程序MCMG及从ENDF/B-Ⅶ库制作的47群P5中子截面库G47B7P5N.MCMG程序发展了针对物质的碰撞机制,适合ANISN格式和非标准ANISN格式的多群中子截面.程序计算了6个临界基准模型和2个外源问题,模拟取得了与实验和连续截面MCNP程序一致的结果,计算速度较MCNP程序提高3倍以上.%The 3-D multigroup P5 neutron transport Monte-Carlo code MCMG was developed and the 47 groups P5 neutron cross-section library G47B7P5N was produced from ENDF/B^VH library. A new collision mechanism about the material was added. The various multigroup cross-sections of the standard and nonstandard ANISN format could be used. Almost the same results with experiments and point-wise cross-section MCNP code were obtained by six critical benchmarks and two external source problems to be simulated. The speedup of MCMG is over three times relative to the MCNP in speed.