三氧化铀中Pu和Np的α放射性比活度分析

    Analysis of α Specific Activity of Plutonium and Neptunium Impurities in Uranium Trioxide

    • 摘要: 三氧化铀中Pu和Np的α放射性比活度是产品质量质控的重要参数。本研究基于TEVA树脂建立高铀样品中Pu和Np放射性比活度α谱仪准确测量的方法。该方法首先将铀氧化物粉末溶解到2 mL的5 mol/L HNO3中,加入0.1 mL 30% (质量分数)H2O2将Pu和Np调节为+4价;随后用TEVA树脂吸附Pu和Np,并用10 mL 5 mol/L HNO3+0.1 mL 30% H2O2溶液洗涤树脂去除干扰元素U,最后用10 mL 0.3 mol/L HNO3+0.02 mol/L H2C2O4溶液洗脱Pu和Np。实验表明:99%以上的U穿透树脂而被去除,U的去污因子>3.2×104,Pu和Np的回收率>90%,适用于0.1~0.5 g三氧化铀中Pu和Np的放射性比活度测量。加标实验结果表明期望值与测量值吻合,相对偏差在−2%~5%之间。空白流程的分析结果证明,当三氧化铀样品取样量为0.2 g时,本方法对Pu和Np的检出限为2.7 Bq/g,满足后处理工艺对铀氧化物粉末中Pu和Np放射性比活度的分析要求。

       

      Abstract: The α specific activity of plutonium(Pu) and neptunium(Np) in the uranium trioxide product is an important parameter for the quality control. In this study, a simple and reliable method based on TEVA resin was established for the determination of α specific activity of Pu and Np using α spectrometer measurement in the high-uranium content sample. In this method, the uranium oxide powder was first completely dissolved into 2 mL of 5 mol/L HNO3 with heating at 90 ℃, then 10 mL of 5 mol/L HNO3 was added, followed by the addition of 0.1 mL of 30%(mass fraction) H2O2 to adjust the valence of Pu and Np to +4. Then the Pu and Np with the high-uranium extracted onto TEVA resin on the condition of 5 mol/L HNO3+0.1 mL 30% H2O2 loading, while the most of interfering element U penetrated the resin, and the rest was removed using 10 mL of 5 mol/L HNO3+0.1 mL 30% H2O2 elute. The losses of Pu and Np were between 1% and 6% in the loading and rinsing fraction. Finally, the Pu and Np were simultaneously eluted with 10 mL of 0.3 mol/L HNO3+0.02 mol/L H2C2O4 at a flow rate of 1 mL/min. The results show that more than 99% of U is removed through the resin separate ion: the decontamination factor of U is greater than 3.2×104 using the method. And the overall recoveries of Np and Pu are >90%, illustrating that the developed method is suitable for the α specific activity measurement of Pu and Np in 0.1-0.5 g of uranium trioxide sample. For the analysis of six spiked samples with known amounts of Pu and Np activities, the measured values are consistent with the expected ones, the relative deviations are between −2% and 5%, indicating the robust and reliable of the developed method. The analysis of the blank procedure shows that the measurement results of Pu and Np are between 0.8 Bq and 1.3 Bq, the detection limit is 2.7 Bq/g for the 0.2 g of uranium trioxide, which meets the requirements of the spent fuel reprocessing process for the determination of α specific activity of Pu and Np in uranium oxide powder. The method has been applied to the determination of Pu and Np impurities in post-treated uranium oxides.

       

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