Recovery and purification of plutonium in lean plutonium product stream obtained during reprocessing of fast reactor spent fuels

被引：1
|
作者：
Govindan, P. [1 ]
Vijayan, K. S. [1 ]
Kumar, G. Santhosh [1 ]
Vijayakumar, V. [1 ]
Venkataraman, M. [1 ]
Natarajan, R. [1 ]
机构：
[1] Indira Gandhi Ctr Atom Res, Reproc Grp, Reproc Plant Operat Div, Kalpakkam 603102, Tamil Nadu, India
来源：
JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY | 2013年 / 295卷 / 01期
关键词：
Anion exchange resin; Dowex 1X4 (50-100 mesh); Decontamination factor; Pre-concentration; Precipitation; ANION-EXCHANGE; TECHNOLOGY;
D O I：
10.1007/s10967-012-2194-z
中图分类号：
O65 [分析化学];
学科分类号：
070302 ; 081704 ;
摘要：
A method has been developed for final purification of plutonium from uranium and fission products of high beta gamma activity. This method involves selection of a suitable ion exchange resin for the purification of plutonium in order to deliver a quality PuO2 product. The effect of the concentration of uranium and plutonium, effect of increased loading of uranium and number of bed volumes for effective washing, which are some of the parameters that generally affect the recovery and purification of plutonium were investigated. An excellent decontamination factor for fission products has been achieved by this anion exchange process which in turn delivered an excellent PuO2 product quality in terms of purity and associated beta gamma activity with low personnel radiation exposure.
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收藏
页码：307 / 313
页数：7
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