利用 90Sr - 源研究吸附剂的抗辐射能力

O. Sych, Yu. M. Kilivnik, M. M. Pop, H. V. Vasylyeva, V. Lazur, O. H. Okunev
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引用次数: 0

摘要

净化水溶液使其免受放射性污染是当今一个极为重要的科学课题。许多有机和无机吸附剂都可用于吸附水溶液中的重金属离子和放射性核素,或用作储存和处理放射性废物的载体。由于放射性核素是电离辐射源,因此吸附剂的抗辐射性是其重要特征。这些研究旨在探讨硅酸钛在强β辐射环境下的行为及其吸附特性的变化或不变性。实验技术描述了溶胶-凝胶法合成硅酸钛吸附剂及其对 Ba2+ 阳离子吸附能力的研究。在溶液 pH 值为中性的批处理条件下研究了 Ba2+ 阳离子的吸附情况。用 Na-EDTA 直接络合滴定法控制 Ba2+ 阳离子的初始浓度和残余浓度,并用 Eriochrom Black T 作为指示剂。利用安装在国立乌日霍罗德大学微电子实验室的 90Sr-90Y β - 源 "天狼星",对吸附剂的高能 β - 辐射抗性进行了研究。光源到吸附剂样品的距离为 20 厘米。在这个距离上的电子通量为每秒 108 艾耳/平方厘米。90Sr 和 90Y β 粒子的最大能量分别为 0.456 兆电子伏特和 2.28 兆电子伏特。辐照时间最长为 21 天,相当于 1310 Gy。使用安装在乌日霍罗德国立大学科学设备集体使用中心 "实验和应用物理实验室 "的拉曼光谱仪 XploRA PLUS 对辐照和未辐照的钛硅样品进行了拉曼光谱分析。研究结果包括硅酸钛和辐照硅酸钛吸附 Ba2+ 的动力学、Ba2+ 吸附等温线以及未辐照、辐照硅酸钛(TiSi)和吸附 Ba2+ 后硅酸钛的拉曼光谱。结果表明,在置信度为 95% 的条件下,最大吸附值为 140.5±9.2 mg/g(6.55%)。辐照硅酸钛和非辐照硅酸钛对钡离子的吸附值相吻合。这表明这种吸附剂的吸附特性在这种辐射剂量的影响下没有发生变化。辐照硅酸钛和未辐照硅酸钛的拉曼光谱相吻合,但没有发现自由基或离子形态,这表明吸附剂的性质在贝塔辐射影响下发生了变化。可以说,这种吸附剂对辐射剂量为 1310 Gy 的 β 辐射具有抗辐射性。本研究的主要结论是,所研究的硅酸钛样品具有抗辐射性。它可以承受 1310 Gy 的辐射剂量而不改变其吸附特性。硅酸钛可用于吸附锶放射性核素,也可作为处理放射性废物的载体。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Investigation of radiation resistance of adsorbents using the 90Sr – source
Purifying aqueous solutions from radioactive contamination is an extremely relevant scientific topic today. Many organic and inorganic adsorbents can be recommended for the adsorption of heavy metal ions and radionuclides from aqueous solutions, or as carriers for storage and disposal of radioactive waste. Since radionuclides are sources of ionizing radiation, the radiation resistance of the adsorbent is an important characteristic. These studies aim to investigate the titanium silicate behavior and its adsorption properties' changes or their invariability in the field of intense β-radiation. Experimental techniques describe the synthesis of titanium silicate adsorbent by sol-gel method and the study of its adsorption capacity toward Ba2+ cations. The adsorption of Ba2+ cations was investigated under batch conditions with neutral pH of the solution. Initial and residual concentrations of Ba2+ cations were controlled by direct complexometric titration with Na-EDTA with Eriochrom Black T as an indicator. The study of the radiation resistance of the adsorbent to high-energy β-radiation was performed using a 90Sr-90Y β- - source “Sirius” installed in the Microtron Laboratory of the Uzhhorod National University. The distance from the source to the adsorbent samples was 20 cm. The flux of electrons at this distance was 108 el/cm2‧per second. The maximum energy of beta particles was 0.456 MeV for 90Sr and 2.28 MeV for 90Y. The maximum duration of exposure was 21 days, which corresponds to 1310 Gy. Raman spectroscopy of irradiated and nonirradiated samples of TiSi was performed using a Raman spectrometer XploRA PLUS installed in the Center for Collective Use of Scientific Equipment “Laboratory of Experimental and Applied Physics” of Uzhhorod National University. Results consist of kinetic of Ba2+ adsorption by titanium silicate and irradiated titanium silicate; isotherm of Ba2+ adsorption and Raman spectrum of nonirradiated, irradiated titanium silicate (TiSi) and TiSi after Ba2+ adsorption. Results showed that the value of the maximal adsorption was 140.5±9.2 mg/g (6.55 %) under a confidence level of 95 %. The adsorption values of barium ions by irradiated and non-irradiated titanium silicate coincide. This indicates that the adsorption properties of this adsorbent do not change under the influence of such a radiation dose. The Raman spectra of irradiated and non-irradiated titanium silicate coincide, while they do not identify free radicals, or ionic formations, which would indicate a change in the properties of the adsorbent under the influence of beta radiation. It can be argued that this adsorbent is radiation-resistant to beta-radioactivity, with a radiation dose of 1310 Gy. The main conclusion of the present work is that the studied sample of titanium silicate is radiation-resistant. It can withstand a radiation dose of 1310 Gy without changing its adsorption properties. Titanium silicate can be used for the adsorption of strontium radionuclides, it can be a carrier for the disposal of radioactive waste.
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