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<p>This study investigated the electrolytic reduction of kilogram-scale U₃O₈ pellets in molten LiCl and focused on optimizing the process for nuclear fuel cycle applications. Critical developments included resolving carbon impurity issues in LiCl, implementing a sequential kerosene-cyclohexane washing process at 150&#xa0;°C for lithium anode pretreatment, and establishing optimal pellet fabrication parameters. By adjusting the sintering atmosphere, the pellet density (4.5–8.5&#xa0;g/cm<sup>3</sup>) and chemical composition (U₃O₈ or U₄O₉) could be controlled. The electrolytic reduction used a stainless-steel cathode basket loaded with sintered pellets and a lithium metal counter electrode. The experiment was conducted in an inert-atmosphere glove box for 181h. The results showed reduction extents of 99.09% for U₃O₈ and 99.17% for U₄O₉, a uranium metal production rate of 55.7&#xa0;gU/h, and a current efficiency of 56.1%. X-ray diffraction analysis confirmed that the primary reduction products were metallic uranium and uranium carbide.</p>

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Study on the electrolytic reduction of kilogram-scale U3O8 in molten LiCl

  • 期刊论文

  • 发表日期：

    2026年2月26日

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  • Benlin Yao,
  • Guangzhi Ren,
  • Hongwei Jia,
  • Mingshuai Yang,
  • Xun Li,
  • Xiao Liu,
  • Jing Sun,
  • Sijing Liu,
  • Yiqun Xiao,
  • Zhaokai Meng,
  • Peng Song,
  • Hui Chen,
  • Qiuyue Zhang,
  • Lei Zhang,
  • Rushan Lin,
  • Guoan Ye,
  • Hui He

摘要

This study investigated the electrolytic reduction of kilogram-scale U₃O₈ pellets in molten LiCl and focused on optimizing the process for nuclear fuel cycle applications. Critical developments included resolving carbon impurity issues in LiCl, implementing a sequential kerosene-cyclohexane washing process at 150 °C for lithium anode pretreatment, and establishing optimal pellet fabrication parameters. By adjusting the sintering atmosphere, the pellet density (4.5–8.5 g/cm3) and chemical composition (U₃O₈ or U₄O₉) could be controlled. The electrolytic reduction used a stainless-steel cathode basket loaded with sintered pellets and a lithium metal counter electrode. The experiment was conducted in an inert-atmosphere glove box for 181h. The results showed reduction extents of 99.09% for U₃O₈ and 99.17% for U₄O₉, a uranium metal production rate of 55.7 gU/h, and a current efficiency of 56.1%. X-ray diffraction analysis confirmed that the primary reduction products were metallic uranium and uranium carbide.