M. N. Belonogov, N. D. Dyrda, G. N. Rykovanov, I. V. Sannikov, P. A. Sannikova, V. A. Simonenko, V. G. Subbotin, R. R. Fazylov, D. V. Khmelnitsky, V. A. Shelan, O. V. Shults
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A study of plutonium fluoride solubility in LiF–BeF2 melt for the substantiation of a molten salt reactor for Np, Am, Cm transmutation
The paper presents a justification, setting, and results of experiments on the determination of the liquidus temperature for a molten salt comprised of 73LiF–27BeF2 with plutonium trifluoride, considered as the fuel circuit salt of a liquid-salt reactor for burning Np, Am, Cm. The liquidus temperature of the melt was determined using a differential scanning calorimetry method; the plutonium concentration in the samples was controlled by recording the γ‑radiation of plutonium isotopes. According to the results of the studies, the liquidus temperature comprised 600–680 °C across a range of plutonium trifluoride concentrations from 0.1–3 mol.%. According to the performed calculations, in order to transmute 250 kg/year of Np, Am, Cm in an MSR‑T reactor, this restriction on the concentration of actinide fluorides in the fuel salt at its operating temperature in the reactor of 650–750 °C requires 550–660 kg/year of plutonium.
期刊介绍:
Atomic Energy publishes papers and review articles dealing with the latest developments in the peaceful uses of atomic energy. Topics include nuclear chemistry and physics, plasma physics, accelerator characteristics, reactor economics and engineering, applications of isotopes, and radiation monitoring and safety.