Separation and recovery study of uranium from spent NaF (fillers)
Separation and recovery study of uranium from spent NaF (fillers)
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DOI：
10.1016/j.jpcs.2004.07.019
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发表时间：
2005-02
影响因子：
4
通讯作者：
Ippei Amamoto;T. Terai;H. Oobayashi;Reiko Fujita
中科院分区：
文献类型：
--
作者：
Ippei Amamoto;T. Terai;H. Oobayashi;Reiko Fujita
熔盐技术被认为是一种可行的从废NaF（填料）中脱除铀的技术。本实验以简单废NaF或NaF与NaCl（即混合盐）作为电解液，以槽内铀浓度、预处理条件、电解温度、电流密度等为参数。基础实验结果表明，熔盐技术在废NaF脱除铀方面具有潜在的适用性。
The molten salt technique is considered to be a feasible technique applicable for the removal of uranium from the spent NaF (fillers). Simple spent NaF or NaF with NaCl, i.e. mixed salt, was used as an electrolyte and the uranium concentrations in the bath, pre-treatment condition, electrolytic temperature, current density, etc. were given as parameters in this experiment. Results from the fundamental experiments showed the potential applicability of the molten salt technique for the removal of uranium from spent NaF.