1. SHOJAA AYED ALJASAR - School of Nuclear Science and Engineering, Tomsk Polytechnic University, Tomsk, Russia.
2. A. G. NAYMUSHIN - School of Nuclear Science and Engineering, Tomsk Polytechnic University, Tomsk, Russia.
3. M.M. AISH - Physics department, Faculty of science, Menoufia University, Egypt.
Loading the composite core of a reactor with mixed uranium oxide (MOX) is essential for fuel campaigning. Moreover, low-enriched uranium (LEU) fuels are used in commercial power reactors, with proven computing methodologies to accurately predict neutron distributions. Neutronics programs are essential in the study of mixed uranium–plutonium oxides at low uranium enrichments for a light-water reactor, such as WWER-1000. Inquiries into both computational and experimental benchmarks are made. The first collisionprobability methodology was supported by GETERA and SERPENT softwares and used to study the neutronic attributes of those bands under various reactor statuses. New computational methods for the (UO2 + Gd) and (UO2 + PuO2 + Gd) fuel assemblies are expected by the Organization for Economic Cooperation and Development (OECD) for use in the WWER-1000. In this paper, a burnup-computing benchmark is presented, representing the simulation that is expected for use in the plutonium-disposal task. The aim of this work is to analyze the results in term of the GETERA and SERPENT softwares tool, checking the BNAB-93 nuclear-data library for results already received within the benchmark.
Benchmark model, Burnup, First collision probability’s method, LEU and MOX, WWER1000, Neutronic calculations GETERA software tool, Numerical simulation, Pressurized water reactor, Reactivity effect, SERPANT.