基于MCNP的压力容器快中子注量率计算参数敏感性分析

Parameter Sensitivity Analysis of Pressure Vessel Fast Neutron Fluence Rate Calculation Based on MCNP

摘要: 本文以NUREG/CR-6115PWR压力容器注量计算基准题中的标准堆芯装载模式为基础，使用MCNP程序及基于ENDF/B-Ⅵ库的连续能量截面库对其进行了压力容器快中子注量率（E＞1.0 MeV）的计算，并在此基础上对截面库、燃耗、裂变谱以及NONU卡等影响计算精度的因素进行了敏感性分析。结果表明，上述参数对基准模型快中子注量率的影响分别为4.12%、5.5%～7.6%、18%和6.7%左右。

Abstract: The pressure vessel fast neutron fluence rates of NUREG/CR-6115PWR were calculated on the basis of the standard core loading problem, by using the MCNP code and ENDF/B-Ⅵ continuous energy cross-section library. And the parameters affecting the calculation accuracy such as the cross-section libraries, burn-up, fission spectrum and NONU card, were calculated for the sensitivity analysis. The results show that the effects of the benchmark model parameters on fast neutron fluence rates are 4.12%, 5.5%-7.6%, 18% and 6.7% or so.