부산대학교 도서관

Calculation of the core neutronic parameters is one of the key components in all nuclearreactors. In this research, the energy spectrum and spatial distribution of the neutron fluxin a uranium target have been calculated. In addition, sensitivity of the core neutronicparameters in accelerator-driven subcritical advanced liquid metal reactors, such aselectron beam energy (Ee) and source multiplication coefficient (ks), has been investigated. A Monte Carlo code (MCNPX_2.6) has been used to calculate neutronic parameters such aseffective multiplication coefficient (keff), net neutron multiplication (M), neutron yield (Yn/e), energy constant gain (G0), energy gain (G), importance of neutron source (4*), axial andradial distributions of neutron flux, and power peaking factor (Pmax/Pave) in two axial andradial directions of the reactor core for four fuel loading patterns. According to the results,safety margin and accelerator current (Ie) have been decreased in the highest case of ks, butG and 4* have increased by 88.9% and 21.6%, respectively. In addition, for LP1 loadingpattern, with increasing Ee from 100 MeV up to 1 GeV, Yn/e and G improved by 91.09% and10.21%, and Ie and Pacc decreased by 91.05% and 10.57%, respectively. The results indicatethat placement of the NpePu assemblies on the periphery allows for a consistent keffbecause the NpePu assemblies experience less burn-up.