In this study, the chlorination of uranium oxide (UO₂) using ammonium chloride and zirconium as chemical agents was conducted to recover the uranium in the anode basket residues from the pyrochemical process of used nuclear fuel. The chlorination of UO₂ was predicted using thermodynamic equilibrium calculations. The experimental conditions for the chlorination were determined using a chlorination test with cerium oxide (CeO₂). In the chlorination test, it was confirmed that UO₂ was chlorinated into UCl₃ at 320 °C, some UO₂ remained without changes in the chemical form, and ZrO₂, Zr₂O, and ZrCl₂ were generated as byproducts.

中文翻译：

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废核燃料热解过程中阳极篮残渣中铀的回收研究

在这项研究中，使用氯化铵和锆作为化学试剂对铀氧化铀（UO ₂）进行氯化，以从废旧核燃料的热化学过程中回收阳极篮残余物中的铀。使用热力学平衡计算预测了UO ₂的氯化。使用氧化铈（CeO ₂）的氯化试验确定氯化的实验条件。在氯化试验中，确认了UO ₂在320℃下被氯化成UCl ₃，残留了一些UO ₂且化学形态没有变化，并且ZrO ₂，Zr ₂ O和ZrCl ₂仍然存在。 产生为副产物。