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- 저자 : Sayed Amier Hossian Feghhi (검색결과 2 건)
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Marziye Ebrahimkhani,Mostafa Hassanzadeh,Sayed Amier Hossian Feghhi,Darush Masti 한국원자력학회 2016 Nuclear Engineering and Technology Vol.48 No.1
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.
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Ebrahimkhani, Marziye,Hassanzadeh, Mostafa,Feghhi, Sayed Amier Hossian,Masti, Darush Korean Nuclear Society 2016 Nuclear Engineering and Technology Vol.48 No.1
Calculation of the core neutronic parameters is one of the key components in all nuclear reactors. In this research, the energy spectrum and spatial distribution of the neutron flux in a uranium target have been calculated. In addition, sensitivity of the core neutronic parameters in accelerator-driven subcritical advanced liquid metal reactors, such as electron beam energy ($E_e$) and source multiplication coefficient ($k_s$), has been investigated. A Monte Carlo code (MCNPX_2.6) has been used to calculate neutronic parameters such as effective multiplication coefficient ($k_{eff}$), net neutron multiplication (M), neutron yield ($Y_{n/e}$), energy constant gain ($G_0$), energy gain (G), importance of neutron source (${\varphi}^*$), axial and radial distributions of neutron flux, and power peaking factor ($P_{max}/P_{ave}$) in two axial and radial directions of the reactor core for four fuel loading patterns. According to the results, safety margin and accelerator current ($I_e$) have been decreased in the highest case of $k_s$, but G and ${\varphi}^*$ have increased by 88.9% and 21.6%, respectively. In addition, for LP1 loading pattern, with increasing $E_e$ from 100 MeV up to 1 GeV, $Y_{n/e}$ and G improved by 91.09% and 10.21%, and $I_e$ and $P_{acc}$ decreased by 91.05% and 10.57%, respectively. The results indicate that placement of the Np-Pu assemblies on the periphery allows for a consistent $k_{eff}$ because the Np-Pu assemblies experience less burn-up.
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