| Summary: | BackgroundBased on the research of molten salt reactor (MSR), a conceptual design of small MSR core with thermal power of 100 MWt is proposed to meet the power supply demand of small area. By adjusting the initial fuel load of the reactor core, the reactor can operate at full power for 1 250 days without refueling, and then batch process fuel at the end of its life.PurposeThis study aims to analyze the yield and source of radionuclides in the main loop during such a small MSR operation by providing the constitutions, main components, and parameters according to the burnup characteristics and fuel salt characteristics of the long refueling cycle.MethodsThe calculation software KENOVI for three-dimensional Monte Carlo transportation program and burnup analysis module Origen-S were employed to analyze the fuel consumption analysis module, the storage of radioactive products in the main loop and the neutron energy spectrum and other neutron parameters.ResultsThe computation results show that the radioactivity at the end-of-life this small MSR is about 7.36×1018 Bq, and the radioactivity of fission products in the end-of-life primary loop is about 5.89×1018 Bq, of which the inert gases, iodine isotopes and the volatile fission metal account for 7.35×1017 Bq, 9.56×1017 Bq, 8.17×1017 Bq respectively. The total radioactivity of actinide nuclides is about 1.47×1018 Bq, of which the 239Np accounts for 98%.ConclusionsThis study provides reference for radiation protection design and fuel reprocessing scheme of molten salt reactor.
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