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Investigation of PuF3 and AmF3 Solubility in 73LiF–27BeF2 Melt

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Atomic Energy Aims and scope

Using an experimental stand for studying the solubility of fluorides, measurements were performed at 550–700°C with step 50°C and the solubility of plutonium and americium trifluorides in melt with molar composition 73LiF–27BeF2 was calculated. Previously, such measurements were not performed for plutonium and americium trifluoride. The temperature dependence of the solubility of plutonium and americium trifluoride for the given salt system was constructed. The obtained solubility for plutonium trifluoride is appreciably higher than in a similar salt system with a higher content of beryllium difluoride. The obtained data on the solubility of americium and plutonium trifluoride can be used to select the minimum temperature of the fuel salt of a molten-salt reactor.

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Authors and Affiliations

  1. State Science Center of the Russian Federation – Research Institute of Atomic Reactors (SSC RIAR), Dimitrovgrad, Russia

    A. A. Lizin, S. V. Tomilin, A. G. Osipenko & N. Yu. Nezgovorov

  2. National Research Center Kurchatov Institute, Moscow, Russia

    V. V. Ignat’ev & M. V. Kormilitsyn

Authors
  1. A. A. Lizin
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  2. S. V. Tomilin
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  3. A. G. Osipenko
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  4. N. Yu. Nezgovorov
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  5. V. V. Ignat’ev
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  6. M. V. Kormilitsyn
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Corresponding author

Correspondence to V. V. Ignat’ev.

Additional information

Translated from Atomnaya Énergiya, Vol. 126, No. 6, pp. 321–324, June, 2019.

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Lizin, A.A., Tomilin, S.V., Osipenko, A.G. et al. Investigation of PuF3 and AmF3 Solubility in 73LiF–27BeF2 Melt. At Energy 126, 368–371 (2019). https://doi.org/10.1007/s10512-019-00566-6

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  • DOI: https://doi.org/10.1007/s10512-019-00566-6

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