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Preparation of uranium(III) in a molten chloride salt: a redox mechanistic study
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 BiCl(3) has been performed for...
Autores principales: | , , |
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Formato: | Online Artículo Texto |
Lenguaje: | English |
Publicado: |
Springer International Publishing
2018
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Materias: | |
Acceso en línea: | https://www.ncbi.nlm.nih.gov/pmc/articles/PMC6061103/ https://www.ncbi.nlm.nih.gov/pubmed/30100650 http://dx.doi.org/10.1007/s10967-018-5953-7 |