摘要
本文评论了世界各国乏燃料后处理技术。后处理能力在目前和不久将来不能满足核能的发展需要,它在燃料循环中占有重要的地位。普雷克斯流程不仅对于轻水堆燃料,而且对快中子增殖堆燃料后处理然是一种主要流程。近期后处理研究和发展的重点在于使流程最佳化,并引入新技术,尤其是U(Ⅳ),电解氧化还原,硝酸羟胺还原和亚硝气氧化等无盐过程。当处理高燃耗的乏燃料时,应采取特别措施,以避免造成溶剂的严重辐解和钚的临界问题。氚在流程中必须控制,并限定在一定区域,使其废液体积尽量减小。
A survey of reprocessing of spent fuel elements over the world was made. The capacity of reprocessing does not fulfill the needs of nuclear power development at present and in the near future. The reprocessing remains its important position in the fuel cycle. The Purex process is still the main process not only for LWR fuel but also for FBR fuel. The recent R & D of reprocessing is focused on the improvement and the optimization of the process, especially on the so called salt free process including U4+,electro-reduction and oxidation, hydroxylamine, nitrous oxide and so forth. Processing of spent fuel with high burn-up should take special measure in order to avoid heavy radiolytic degradation of the solvent and the criticality of plutonium. Tritium must be controlled and confined in the definite area of the process in a small volume.
出处
《核化学与放射化学》
CAS
CSCD
北大核心
1991年第4期199-207,共9页
Journal of Nuclear and Radiochemistry
关键词
核燃料
后处理
普雷克斯流程
辐解
Reprocessing, Fuel element, Purex process, Degradation, Solvent extraction, Uranium, Neptunium, Plutonium, Tritium.
