Cloth filter for recovery of uranium from radioactive waste
Cloth filter for recovery of uranium from radioactive waste
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DOI：
10.1016/j.radphyschem.2004.08.003
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发表时间：
2005-06-01
影响因子：
2.9
通讯作者：
Hashem, A
中科院分区：
文献类型：
--
作者：
Badawy, SM;Sokker, HH;Hashem, A
合成了一种含偕胺肟/羧基的滤布，用于从核燃料制造实验室的放射性废物中回收铀。通过辐射诱导丙烯腈/甲基丙烯酸（AN/MA）接枝到棉布上，然后在AN与MA的重量比为80/20下进行酰胺肟化反应来合成滤布过滤器。研究了共聚单体组成对接枝率和接枝链中AN含量的影响。AN对棉织物的接枝反应活性低于MA酸。通过FT-IR光谱证实了官能团的引入。该滤布具有良好的机械性能、热稳定性和化学稳定性，适合于实际应用。在298 K和pH 9-9.5条件下，铀的吸收率达到95%。(c)2004爱思唯尔有限公司保留所有权利。
A cloth filter incorporated with amidoxime/carboxyl groups was synthesized for recovery of uranium from radioactive waste obtained from nuclear fuel fabrication laboratories. The cloth filter was synthesized by radiation-induced grafting of acrylonitrile/methacrylic acid (AN/MA) onto a cotton cloth and followed by amidoximation reaction at a weight ratio of AN to MA of 80/20. The effect of comonomer composition on the grafting ratio and AN composition in the graft chain was studied. The reactivity of AN for grafting into the cotton cloth was found to be less than that of the MA acid. The incorporation of the functional groups was confirmed by FT-IR spectra. The cloth filter possessed good mechanical properties and thermal and chemical stability suitable for practical use. The uranium uptake ratio reached 95% at 298 K and pH 9-9.5. (c) 2004 Elsevier Ltd. All rights reserved.