A study of plutonium fluoride solubility in LiF-BeF.sub.2 melt for the substantiation of a molten salt reactor for Np, Am, Cm transmutation

• Published in: Atomic energy (New York, N.Y.) N.Y.), 2023-05, Vol.134 (1-2), p.73
• Main Authors: Belonogov, M. N, Dyrda, N. D, Rykovanov, G. N, Sannikov, I. V, Sannikova, P. A, Simonenko, V. A, Subbotin, V. G
• Format: Article
• Language: English
• Subjects: Calorimetry; Fluorides; Nuclear energy; Nuclear fuel cycle; Plutonium; Radiation
• ISSN: 1063-4258
• DOI: 10.1007/s10512-023-01029-9

The paper presents a justification, setting, and results of experiments on the determination of the liquidus temperature for a molten salt comprised of 73LiF-27BeF.sub.2 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 [gamma]âradiation 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 0.1-3â¯mol.%. According to the performed calculations, in order to transmute 250â¯kg/year of Np, Am, Cm in an MSRâT 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 550-660â¯kg/year of plutonium.