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

摘要

Quantification of activation in structure materials around a nuclear reactor using results of neutron shielding calculations is necessary for efficient planning of decommissioning. In this study, the random sampling method is applied to the neutron shielding calculation in order to estimate uncertainties of neutron flux and activation of ~(59)Co in structure materials due to cross section covariance. The calculation results indicate that the magnitude of uncertainty of activation of ~(59)Co due to cross section data is approximately 15～30% inside structure materials.