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Rapid separation of zirconium using microvolume anion-exchange cartridge for 93Zr determination with isotope dilution ICP-MS
Talanta ( IF 6.1 ) Pub Date : 2018-03-14 , DOI: 10.1016/j.talanta.2018.03.026
Shiho Asai , Yukiko Hanzawa , Miki Konda , Daisuke Suzuki , Masaaki Magara , Takaumi Kimura , Ryo Ishihara , Kyoichi Saito , Shinsuke Yamada , Hideyuki Hirota

Estimating the risks associated with radiation from long-lived fission products (LLFP) in radioactive waste is essential to ensure the long-term safety of potential disposal sites. In this study, the amount of 93Zr, a LLFP, was determined by ICP-MS after separating Zr from a spent nuclear fuel solution using a microvolume anion-exchange cartridge (TEDA cartridge). Zirconium in 9.4 M HCl was stably retained on the TEDA cartridge and readily eluted with 0.75 mL of a mixed solution of 9.4 M HCl and 0.01 M HF. The time taken to complete the Zr separation was 1.2 min. Almost all the other elements initially present in the spent nuclear fuel sample were removed, leading to accurate measurement of all six Zr isotopes (90Zr, 91Zr, 92Zr, 93Zr, 94Zr, and 96Zr). This demonstrated that the TEDA cartridge allowed highly selective separation of Zr regardless of its small bed volume of 0.08 cm3. The concentrations of these isotopes were determined by an isotope-dilution method using a natural Zr standard that has a different isotopic composition from that of the spent nuclear fuel sample. The amount of 93Zr in an initial spent nuclear fuel pellet was 1081 ± 79 ng per mg of 238U. The measured concentrations of all Zr isotopes, as well as the isotopic composition, were consistent with values predicted using a burnup calculation code.



中文翻译:

使用微量阴离子交换盒快速分离锆,用于同位素稀释ICP-MS测定93 Zr

估计与放射性废物中长寿命裂变产物(LLFP)的辐射有关的风险对于确保潜在处置场所的长期安全至关重要。在这项研究中,使用微体积阴离子交换滤芯(TEDA滤芯)从乏核燃料溶液中分离Zr之后,通过ICP-MS测定93 Zr(LLFP)的含量。将9.4 M HCl中的锆稳定地保留在TEDA滤芯上,并轻松用0.75 mL 9.4 M HCl和0.01 M HF的混合溶液洗脱。完成Zr分离所需的时间为1.2分钟。几乎消除了乏核燃料样品中最初存在的所有其他元素,从而可以精确测量所有六个Zr同位素(90 Zr,91 Zr,92 Zr,93 Zr,94 Zr和96 Zr)。这表明,TEDA滤筒可实现Zr的高度选择性分离,而无需考虑其0.08 cm 3的小床体积。这些同位素的浓度是使用天然Zr标准品通过同位素稀释法确定的,该标准品的同位素组成与乏核燃料样品的同位素组成不同。初始乏核燃料芯块中93 Zr的量为每238 U毫克1081±79 ng 。所有Zr同位素的测定浓度以及同位素组成与使用燃耗计算代码预测的值一致。

更新日期:2018-03-14
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