Computational Validation of Experiments with Molten-Salt Thorium-Uranium Fuel Compositions in MBIR Test Loop

Abstract

The results of calculations of the equilibrium isotopic composition of molten-salt fuel in an experimental channel of the MBIR reactor are presented. Two organizational variants of the fuel cycle for a molten-salt test loop are examined: with extraction of protactinium and without extraction of heavy nuclei. The results show that the maximum thermal power of the test loop channel can reach 12 MW. Reprocessing of the fuel salt at the rate 27.1 kg/day is necessary to maintain the thermal power at the level 1 MW. A brief description is given of the procedure for obtaining an equilibrium isotopic composition in the ISTAR software system.