Uncertainty Quantification of Activation Due to Cross Section Data in Neutron Shielding Calculation

摘要

The RS method is applied to neutron shielding calculation using ANISN/TRANSX in order to estimate uncertainties of neutron flux and activation in a structure material (iron). The calculation results indicate that the magnitude of uncertainty of activation of ~(59)Co due to cross section is approximately 10% inside structural material, which is not very large when attenuation of neutron flux is taken into account.