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溶液堆的应用及其核燃料处理
Application and Spent-Fuel Reprocessing of Solution Reactor
【摘要】 溶液堆在医用同位素的生产方面具有一些优势,本文对溶液堆的发展过程进行了介绍,对用于医用同位素生产的水溶液均相反应堆的技术特点、核素生产以及相关的核燃料处理问题进行了综述。溶液堆可以提取的同位素主要有99Mo,131I,89Sr等。在核燃料处理方面,溶剂萃取法是切实可行的方法,针对硫酸和硝酸2种溶液体系,推荐了硝酸体系的φ=30%TBP流程。溶液堆运行1~2年左右,冷却3~5个月进行后处理,放射性浓度大于99%的裂变和腐蚀产物被去除,铀的回收率大于99.5%,回收的铀可以回堆继续应用,形成一个快速处理循环。在后处理设备方面,小型化的核用离心萃取器及过滤设备是最好的选择。
【Abstract】 The solution reactor has advantages in medico-isotope production.The history of the development of homogeneous solution-type reactor,its technical properties and related fuel reprocessing process have been introduced,mainly for isotopes 99Mo,131I,89Sr.30% TBP solvent extraction reprocess is recommended to treat spent-fuel of homogeneous reactor.The recovery ratio for uranium is more than 99.5% while radio concentration>99% of fission and corrosion products are removed in the reprocess.Solution of spent-fuel can be reprocessed after 1-2 years of operation and cooling for 3-5 months.Small type equipments,such as centrifugal extractors are preferred for the process.
【Key words】 solution reactor; production of medico-isotope; reprocessing;
- 【文献出处】 核化学与放射化学 ,Journal of Nuclear and Radiochemistry , 编辑部邮箱 ,2009年01期
- 【分类号】TL24
- 【被引频次】6
- 【下载频次】302