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Liquidus temperature study of LiF–NaF–KF-based melts simulating the fuel salt of a molten-salt reactor for Np, Am, Cm transmutation

  • M. N. Belonogov,
  • I. A. Volkov,
  • N. D. Dyrda,
  • G. N. Rykovanov,
  • I. V. Sannikov,
  • P. A. Sannikova,
  • R. R. Fazylov,
  • D. V. Khmelnitsky,
  • V. A. Shelan

摘要

Experiments were carried out to determine the liquidus temperature of 46.5LiF–11.5NaF–42KF-based melts simulating the fuel salt of a molten-salt burner operating in a Np, Am, Cm transmutation mode without the consumption of plutonium. The liquidus temperature was determined by differential scanning calorimetry; the melt composition was monitored by atomic emission, alpha, and gamma spectrometry. Melts containing PuF3 and UF4, as well as NdF3 and NiF2 simulating the products of fission and corrosion of structural materials were studied. For the actinide fluoride mole fraction of 5–15 mol% in the LiF–NaF–KF-based fuel salt in the presence of fission and corrosion products, the liquidus temperature of the melts was equal to 485–580 °C.