MCMG蒙特卡罗多群-连续截面耦合中子输运计算

本文针对多群蒙特卡罗计算省时但共振自屏处理存在缺陷，以及连续截面蒙特卡罗输运计算精度高但计算费时的问题，发展了一种多群-连续截面耦合计算方法。该方法在自主研发的三维中子-光子耦合输运蒙特卡罗程序MCMG中得到应用，通过多个模型的计算验证了方法的有效性。MCMG耦合计算取得了与连续点截面MCNP程序一致的结果，其计算速度较MCNP的提高了1倍左右。

Coupled Neutron Transport Calculation of MCMG Monte Carlo Multigroup-Continuous Cross Section

It is well known that the computation time of multigroup Monte Carlo calculation is much less than that of the continuous (point-wise) calculation. However, there are some difficulties in the multigroup treatment about resonance and self-shielding. Although the good precision of point-wise cross section transport calculation can be obtained, the consumed time is too long. A coupled calculation of the multigroup and the point-wise cross section was developed in self-development 3D neutron and photon transport Monte Carlo code MCMG. The validity of this method was proved by testing of many models. The almost same results with the point-wise cross section MCNP code were achieved. The coupled calculation of MCMG is about one time faster than that of MCNP.