乏燃料后处理的概念
Prospects for the worldwide development of nuclear power production suggest that two or three new nuclear power plants will be put into operation yearly till 2030. This scenario gives a greater role to the final stage of the closed nuclear fuel cycle in Russia, namely, the reprocessing of spent nuclear fuel (SNF) in order to separate uranium and plutonium and recycle them into power production.
Several processes are now used for SNF reprocessing, primarily, aqueous processes, the main being the PUREX process [1]. Next are anhydrous or dry processes, such as fluoride gas SNF reprocessing and the electrochemical separation of uranium and plutonium from alkali chloride melts [2]. These processes have both strengths and weaknesses; the elimination of these weaknesses will considerably enhance the development of the processes.
Our strategy of SNF reprocessing develops aqueous processes and is an alternative primarily to the widely used PUREX process. The underlying idea of this strategy is the use of carbonate solutions instead of nitrate solutions, which are widely used for decontaminating uranium and plutonium from fission products, plus extraction.
全球核电生产发展前景表明，到2030年，每年将有两到三个新核电站投入运营。这一设想使俄罗斯封闭核燃料循环的最后阶段发挥了更大的作用，即对乏核燃料进行再处理，以便分离铀和钚并将它们再循环用于电力生产。
目前有几种SNF后处理工艺，主要是水处理工艺，主要是PUREX工艺[1]。接下来是无水或干燥过程，如氟化物气体SNF再处理和电化学分离铀和钚从碱性氯熔体[2]。这些过程既有优点也有缺点;消除这些弱点将大大促进这些进程的发展。
我们的SNF后处理策略发展了水处理工艺，是一种主要替代广泛使用的PUREX工艺的方法。这一战略的基本思想是使用碳酸盐溶液而不是硝酸盐溶液，后者广泛用于从裂变产物中净化铀和钚，并用于萃取。
Studies of some processes that could be used for carbonate reprocessing of SNF started in the late 1950s and early 1960s with studies of the extraction of uranium and thorium by quaternary ammonium salts from carbonate solutions; these studies are reviewed in [3]. Ueno and Saito [4] attempted to ascertain the possibility of the extraction separation of uranium and plutonium from main fission products in carbonate solutions. Machajan et al.
[5] studied plutonium extraction by Aliquat 336 from carbonate solutions. Karalova et al. under the supervision of Academician B.F. Myasoedov performed a series of works on actinide extraction from carbonate and alkali solutions; these works are reviewed in [3]. Considerable advances in carbonate SNF reprocessing were made in Japan; a flowsheet was proposed [6, 7] including the anodic dissolution of UO2-based SNF in a carbonate solution followed by the isolation of uranium and its separation from fission products by precipitation methods.
Further development of carbonate SNF reprocessing occurred at Los Alamos National Laboratory in the United States [8–10]. The reported carbonate process for SNF
