摘要/Abstract

乏燃料后处理是未来先进核燃料循环体系的中心环节, 基于高温熔盐电解的干法后处理技术具有一定优势. 该技术通常在高温氯化物熔盐体系中进行, 采用电化学技术回收锕系元素, 并实现其与镧系元素的电解分离. 其中铀的分离回收是研究的重点之一. 为更好实现铀在熔盐中的分离与回收, 需要深入理解铀的电化学性质与其在熔盐中的配位化学性质的联系. 因此, 开展铀在氯盐体系中的化学种态研究至关重要. 本Review对国际上氯化物熔盐体系中针对铀化学种态的研究进展进行了总结归纳和提炼, 并对未来锕系元素在高温熔盐介质中的化学种态研究进行了展望.
关键词: 干法后处理, 熔盐, 化学种态, 铀
High-temperature molten salt electrolysis based pyrochemical reprocessing of spent nuclear fuel has certain advantages for advanced nuclear fuel cycle, which is usually carried out in a high-temperature chloride molten salt system, and actinides (Ans) are recovered and separated over lanthanides (Lns) via electrolysis in molten salt. Among them, the separation and recovery of uranium from fission products (FPs) is one of the key tasks. To optimize the separation process, it is necessary to deeply understand the relationship between electrochemical properties and chemical species of uranium in molten salt. Hence, it is very important to carry out the study of the chemical species of uranium in molten chlorides. In this review, the research progresses on chemical species of uranium in molten chlorides have been summarized and sorted. In addition, future perspectives upon actinide chemical species in molten salt have been given.
Key words: pyrochemical reprocessing, molten salt, chemical species, uranium


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