Calculation of kinetics parameters for the Dalat Nuclear Reactor (DNR) using MCNP5

The determination of kinetics parameters takes an important role in the safety operation of a nuclear reactor, thus the calculation of these parameters is essential. This paper presents the application of Monte-Carlo method in order to perform the above-mentioned purpose. Two types of calculated kinetics parameters for the Dalat reactor are the effective delayed neutron fraction (β_eff ) and the prompt neutron generation time (l_p). The calculations were performed for the fuel loading patterns of 104 high-enriched uranium (HEU) fuel assemblies and 92 low-enriched uranium (LEU) fuel assemblies. The effective delayed neutron fractions were calculated by prompt method, and the calculated results are 0.80 ± 0.02% for HEU and 0.75 ± 0.03% for LEU fuel loading pattern. The prompt neutron generation times were calculated by 1/v method, and the calculated results are 95.01 ± 1.96 (µs) for HEU and 92.31 ± 2.64 (µs) for LEU fuel loading pattern. The comparison of (β_eff/l_p) ratio between the calculation and previous measurement shows a good agreement. (author)