【摘要】 运用蒙特卡罗方法计算出特殊形状钚材料近距离的中子的能谱、空间分布,避免了用仪器近距离测量的精度受仪器体积影响较大的不足。同时利用注量-剂量转换因子算出近距离中子剂量,为工作人员的安全提供参考。更多还原

【Abstract】 Monte Carlo simulation of neutron spectra and distribution near the surface of spetial shape Pu material can avoid the error caused by the big volume of the detector.And the neutron dose near the Pu material has been calculated with flux-dose conversion factor.It can supply references to the operators’ security.更多还原