Publication: Test task for transmutation of 241Am in molten salt reactors
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2020
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© Published under licence by IOP Publishing Ltd.Molten Salt Reactor (MSR) is one of the six innovative systems, which has been selected by the international Generation IV forum as a candidate for the next-generation reactors. In this paper, the transmutation of241Am, the main contributor to the waste toxicity in the nuclear fuel cycle, in both thermal- and fast-spectrum molten salt reactors is compared. The Am-cylinder is irradiated in the center of the thermal (SD-TMSR) and fast (SMSFR) spectrum MSRs, respectively, and during a long period of time. The total neutron fluxes in SD-TMSR and SMSFR are 4.1×1014 and 1.8×1015 n.cm-2.s-1, respectively. The overall change in actinides and fission products (FPs) mass during the irradiation has been investigated using direct Serpent2 calculations. Under fast spectrum irradiation, transmutation leads to produce short-lived FPs (by fission) rather than the accumulation of heavier actinides. The ratio between the maximum and initial released energy from all isotopes in the Am-cylinder has been calculated in this paper.
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Ashraf, O. Test task for transmutation of 241Am in molten salt reactors / Ashraf, O., Tikhomirov, G.V. // Journal of Physics: Conference Series. - 2020. - 1689. - № 1. - 10.1088/1742-6596/1689/1/012027