Selective ion exchange separation of uranium from concomitant impurities in uranium materials and subsequent determination of the impurities by ICP-OES

被引:25
|
作者
Aziz, A. [1 ]
Jan, S. [1 ]
Waqar, F. [1 ]
Mohammad, B. [1 ]
Hakim, M. [1 ]
Yawar, W. [1 ]
机构
[1] Pakistan Inst Nucl Sci & Technol, Cent Analyt Facil Div, Islamabad, Pakistan
关键词
Uranium; Ion exchange; Ceramic nuclear fuel; ICP-OES; ATOMIC EMISSION-SPECTROMETRY; ANION-EXCHANGE; TRACE IMPURITIES; NUCLEAR-FUEL; PLASMA; THORIUM; EXTRACTION; MATRICES; RESINS; AES;
D O I
10.1007/s10967-009-0444-5
中图分类号
O65 [分析化学];
学科分类号
070302 ; 081704 ;
摘要
An ion exchange method has been developed for the separation of uranium from trace level metallic impurities prior to their determination by inductively coupled plasma optical emission spectrometry (ICP-OES) in uranium materials. Selective separation of uranium from trace level metallic impurities consisting Cr, Co, Cu, Fe, Mn, Cd, Gd, Dy, Ni, and Ca was achieved on anion exchange resin Dowex 1 x 8 in sulphate medium. The resin (100-200 mesh, in chloride form) was packed in a small Teflon column (7.8 cm x 0.8 cm I.D.) and brought into sulphate form by passing 0.2 N ammonium sulphate solution. Optimum experimental conditions including pH and concentration of sulphate in the liquid phase were investigated for the effective uptake of uranium by the column. Uranium was selectively retained on the column as anionic complex with sulphate, while impurities were passed through the column. Post column solution was collected and analyzed by ICP-OES for the determination of metallic impurities. Up to 2,500 mu g/mL of uranium was retained with > 99% efficiency after passing 25 mL sample through the column at pH 3. Percentage recoveries obtained for most of the metallic impurities were > 95% with relative standard deviations < 5%. The method established was applied for the determination of gadolinium in urania-gadolinia (UO2-Gd2O3) ceramic nuclear fuel and excellent results were achieved. Solvent extraction method using tributylphosphate (TBP) as extractant was also applied for the separation of uranium in urania-gadolinia nuclear fuel samples prior to the determination of gadolinium by ICP-OES. The results obtained with the present method were found very comparable with those of the solvent extraction method.
引用
收藏
页码:117 / 121
页数:5
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