Benchmark analysis of SPERT-IV reactor with Monte Carlo code MVP

• MVP was used for SPERT-IV core modeling.
• Neutronics analysis of SPERT-IV reactor was performed.
• Calculation performed to estimate critical rod height, excess reactivity.
• Neutron flux, time integrated neutron flux and Cd-ratio also calculated.
• Calculated values agree with experimental data.

The benchmark experiment of the SPERT-IV D-12/25 reactor core has been analyzed with the Monte Carlo code MVP using the cross-section libraries based on JENDL-3.3. The MVP simulation was performed for the clean and cold core. The estimated values of Keff at the experimental critical rod height and the core excess reactivity were within 5% with the experimental data. Thermal neutron flux profiles at different vertical and horizontal positions of the core were also estimated. Cadmium Ratio at different point of the core was also estimated. All estimated results have been compared with the experimental results. Generally good agreement has been found between experimentally determined and the calculated results.