Total cross-sections of crystalline uranium for thermal neutrons

The total neutron cross-sections of α-uranium (orthorhombic structure) have been calculated from 0.1 meV to 10 eV, using a generalized formula. Computer codes PORU and SORU were developed to calculate the total neutron cross-section and neutron transmission through poly and mono-crystalline uranium respectively. The obtained agreement between the calculated total cross-sections of poly-crystalline uranium in the energy range from 4 meV to 1 eV and the available experimental values justifies the applicability of the used formula and the computer code. A feasibility study on using depleted uranium single crystal as a thermal neutron filter is also given.