Preparation of uranium(III) in a molten chloride salt: a redox mechanistic study.

Preparation of uranium(III) in a molten chloride salt: a redox mechanistic study.
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DOI:
10.1007/s10967-018-5953-7
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发表时间:
2018
影响因子:
1.6
通讯作者:
Sharrad CA
Sharrad CA
中科院分区:
化学4区
文献类型:
--
作者:
Lambert H;Kerry T;Sharrad CA

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废核燃料高温处理的最先进方法是在LiCl-KCl低共熔物中电解精炼铀金属,其中铀溶解为U(III)。在LiCl-KCl低共熔物中通过使用BiCl 3氯化铀金属来生产U(III)已用于研究目的。在这项工作中,通过目视观察,电子吸收光谱和电化学在450 °C下原位研究了该反应。最有可能的机制已被确定为涉及最初的直接氧化铀金属铋(III)的U(IV)。溶解的U(IV)然后与未反应的铀金属反应形成U(III)。
The most advanced methodology for the pyroprocessing of spent nuclear fuel is the electrorefining of uranium metal in LiCl–KCl eutectic, in which uranium is solubilized as U(III). The production of U(III) in LiCl–KCl eutectic by the chlorination of uranium metal using BiCl3 has been performed for research purposes. In this work, this reaction was studied in-situ by visual observation, electronic absorption spectroscopy and electrochemistry at 450 °C. The most likely mechanism has been determined to involve the initial direct oxidation of uranium metal by Bi(III) to U(IV). The dissolved U(IV) then reacts with unreacted uranium metal to form U(III).
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