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干法后处理技术典型流程综述
引用本文:欧阳应根.干法后处理技术典型流程综述[J].中国核科技报告,2001(1).
作者姓名:欧阳应根
作者单位:中国原子能科学研究院放射化学研究所 北京,102413
摘    要:虽然基于溶剂萃取的Purex流程在乏燃料后处理几十年的应用中取得的成功,使得水法后处理至今没有发展出可以取代这一流程的新萃取剂,但干法后处理却有了两种可供进一步发展的流程:氟化物挥发法和高温电化学法。氟化物挥发法存在的最大问题是热力学上PuF6必须在有大量F2过剩的条件下才稳定。高温电化学法适合于处理合金元件,以及氧化物和碳化物元件。首先,将核燃料熔解在熔盐中,然后,电解使铀钚在阴极上沉积,再对阴极上沉积出来的铀钚进行精制而得到铀钚产品。但该方法存在熔盐对MOX的熔解能力和对过程设备的腐蚀问题。

关 键 词:干法  后处理  乏燃料

An Overview on Dry Reprocessing of Irradiated Nuclear Fuels
OUYANG Yinggen China Institute of Atomic Energy,Beijing.An Overview on Dry Reprocessing of Irradiated Nuclear Fuels[J].China Nuclear Science and Technology Report,2001(1).
Authors:OUYANG Yinggen China Institute of Atomic Energy  Beijing
Affiliation:OUYANG Yinggen China Institute of Atomic Energy,Beijing,102413
Abstract:Although spent nuclear fuels have been reprocessed successfully for many years by the well-know Purex process based on solvent extraction, other reprocessing method which do not depend upon the use of organic solvents and aqueous media appear to have important potential advantage. There are two main non-aqueous methods for the reprocessing of spent fuel: fluoride-volatility process and pyro-electrochemical process. The presence of a poser in the process is that PuF6 is obviously thermodynamically stable only in the presence of a large excess of fluorine. Pyroelectrochemical process is suited to processing metallic, oxide and carbide fuels. First, the fuel is dissolved in fresh salts, then, electrodes are introduced into the bath, U and Pu is deposited on the cathode, third, separation and refinement U and Pu is deposited on the cathode. There is a couple of contradictions in the process that are not in harmonious proportion in the fields on the nuclear fuel is dissolved the ability in the molten salt and corrosiveness of the molten salt for equipment used in the process.
Keywords:Dry process  Reprocessing  Irradiated nuclear fuel  
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