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

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.