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Preparation of Microvolume Anion-Exchange Cartridge for Inductively Coupled Plasma Mass Spectrometry-Based Determination of Np-237 Content in Spent Nuclear Fuel

机译:基于电感耦合等离子体质谱法测定废核燃料中Np-237含量的微量阴离子交换小柱的制备

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Microvolume anion-exchange porous polymer disk-packed cartridges were prepared for Am/Np separation, which is required prior to the measurement of Neptunium-237 Np-237 with inductively coupled plasma mass spectrometry (ICPMS). Disks with a volume of 0.08 cm(3) were cut out from porous sheets having anion-exchange-group-containing polymer chains densely attached on the pore surface. Four different amine-based groups, N,N-dimethylaminoethyl methacrylate, trimethylammonium, diethylamine, and triethylenediamine (TEDA), were selected as the anion-exchange groups to be introduced into the porous sheets. The separation performances of Am/Np were evaluated using a standard solution of Am-243, which had the same activity as its daughter nuclide Np-239 in secular equilibrium. Np-239 recovery of close to 100% with practically no contamination of Am-243 was achieved using the TEDA-introduced disk-packed cartridge. The time to elute Np-239 from the cartridge was approximately 40 s. The TEDA-introduced disk-packed cartridge was applied to the separation of Np from a spent nuclear fuel sample to confirm its separation performance. A known amount of Am-243 Np-239 was added to the spent nuclear fuel sample solution to monitor the chemical yield of Np. The chemical yield of Np calculated from a measured concentration of Np-239 was 90.4%. Am leakage in the Np-eluted solution was less than 1 ppt, corresponding to 0.001% of the original Am concentration in the sample. This indicates that no additional Np-239 was produced by the decay of the Am-243 remaining in the Np-eluted solution, thus providing a reliable chemical yield. U, which can cause a serious spectral interference involving the peak tail from the mass spectrum of U-238, was thoroughly removed with the TEDA cartridge, providing interference-free measurement of Np-237. The concentration of Np-237 obtained by ICPMS was 718 +/- 12 ng/mg-U, which agrees well with the theoretically calculated value. Compared with the conventional separation technique using commercially available anion-exchange resin columns, the time required to adsorb, wash, and elute Np using the TEDA- introduced disk-packed cartridge was reduced by 75%.
机译:准备了用于阴离子交换的微体积阴离子交换多孔聚合物盘盒,这在用电感耦合等离子体质谱法(ICPMS)测量Neptunium-237 Np-237之前是必需的。从多孔片材上切下体积为0.08 cm(3)的圆盘,该多孔片材具有紧密附着在孔表面的含阴离子交换基团的聚合物链。选择四种不同的基于胺的基团,即甲基丙烯酸N,N-二甲基氨基乙基酯,三甲基铵,二乙胺和三亚乙基二胺(TEDA)作为要引入多孔片材中的阴离子交换基团。使用Am-243的标准溶液评估Am / Np的分离性能,该溶液在长期平衡下具有与其子核素Np-239相同的活性。使用TEDA引入的磁盘装盒式磁带,可以实现几乎100%的Np-239回收率,几乎不会污染Am-243。从盒中洗脱Np-239的时间约为40 s。引入TEDA的圆盘装药弹药筒用于从乏核燃料样品中分离Np,以确认其分离性能。将已知量的Am-243 Np-239添加到乏核燃料样品溶液中,以监控Np的化学收率。由Np-239的测定浓度算出的Np的化学收率为90.4%。 Np洗脱溶液中的Am泄漏小于1 ppt,相当于样品中原始Am浓度的0.001%。这表明通过Np洗脱溶液中残留的Am-243的降解,不会产生额外的Np-239,从而提供了可靠的化学收率。用TEDA盒彻底清除了U,它可能引起严重的光谱干扰,涉及U-238质谱图中的峰尾,因此可以对Np-237进行无干扰测量。 ICPMS测得的Np-237浓度为718 +/- 12 ng / mg-U,与理论计算值相吻合。与使用市售阴离子交换树脂柱的常规分离技术相比,使用TEDA引入的盘装小柱吸附,洗涤和洗脱Np所需的时间减少了75%。

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