Abstract
Fuel consumption of Iranian miniature neutron source reactor (MNSR) during 15years of operation has been investigated. Reactor core neutronic parameters such as flux and power distributions, control rod worth and effective multiplication factor at BOL and after 15years of irradiation has been calculated.The Monte Carlo-based depletion code system IRBURN has been used for studying the reactor core neutronic parameters as well as the isotopic inventory of the fuel during burnup. The precision and accuracy of the implemented model has been verified via validation the results for neutronic parameters in the MNSR final safety analysis report.The results show that keff decreases from 1.0034 to 0.9897 and the total U-235 consumption in the core is about 13.669g after 15years of operational time. Finally, our studying shows the consumption rate of MNSR is about 1%.
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