3-D Multigroup P₅ Monte-Carlo Neutron Transport Code MCMG and Tests

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-Ⅶ 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.