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Radiological assessment of bauxite residue processing to enable zero-waste valorisation and regulatory compliance

机译:铝土矿残渣加工的放射学评估,使零废物储度和监管依从性

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In this work, the presence of natural radionuclides in bauxite residue subjected to a neutralisation-leaching process and smelting-leaching process was investigated. The radionuclide concentrations of radium-226, radium-228 and thorium-228 were compared with the concentration of the same radio-nuclides in the untreated bauxite residue. It was found that neutralisation of bauxite residue at relatively high temperatures (120-150 degrees C) and high pressure (P-CO2 = 30 bar) did not change the initial concen-tration of radionuclides. In fact, the concentration of radionuclides after an intensive neutralisation process remained below 500 Bq kg(-1). The separation of iron from the rare-earth elements by reductive smelting permitted a significant decrease of iron concentration in the pregnant leach solution obtained after high pressure acid leaching. However, the radionuclide concentration in the slag was increased 1.5 times with respect to the initial concentration, although it did not exceed 800 Bq kg(-1). Further processing of the slags by high pressure acid leaching led to the dissolution of several base metals, while a portion of the radionuclides remained unreacted in the solid fraction. Thus, a concentration of thorium-228 1000 Bq kg(-1) was only observed after leaching a calcium oxide-based slag with hydrochloric acid. Meanwhile, in the leach liquors, the concentration of radionuclides was 100 Bq L-1. Nevertheless, based on analytical estimations using conservative assumptions, the solid residues and leach liquors produced by acid leaching in the current study are unlikely to exceed the exposure limit of 1 mSv set by the European Basic Safety Standards Directive. It should be noted that the current results are based on a specific bauxite residue studied in this work, and caution should be used in the application to other situations. The described radiological assessment of bauxite residue processing can ensure the necessary regulatory compliance and facilitate zero-waste valorisation. (C) 2021 Elsevier Ltd. All rights reserved.
机译:在这项工作中,研究了对经受中和浸出过程和冶炼浸出过程的铝土矿残留物中的天然放射性核素的存在。将放射性核素-226,镭-228和钍-228的放射性核素浓度与未处理的铝土矿残留物中相同的无线电核苷酸的浓度进行比较。发现在相对高的温度下(120-150℃)和高压(P-CO2 = 30巴)中和铝土矿残留物不会改变放射性核素的初始浓度。实际上,在密集中和过程后放射性核素的浓度保持在500bq kg(-1)之后。通过还原冶炼将铁与稀土元素的分离允许在高压酸浸出后获得的妊娠浸出溶液中的铁浓度显着降低。然而,炉渣中的放射性核素浓度相对于初始浓度增加了1.5倍,尽管它不超过800bq kg(-1)。通过高压酸浸出的进一步加工炉渣导致几种基础金属的溶解,而在固体级分中,一部分放射性核素仍未反应。因此,钍-228&gt的浓度;仅在浸出基于氧化钙的炉渣后仅观察到1000bq kg(-1)。同时,在浸出液中,放射性核素的浓度为<100 bq L-1。然而,基于使用保守假设的分析估计,目前研究中酸浸出的固体残留物和浸出液不太可能超过欧洲基本安全标准指令的1 MSV的暴露极限。应当注意,当前结果基于本工作中研究的特定铝土矿残留物,应在申请中使用致防于其他情况。所述铝土矿残留处理的放射学评估可确保必要的调节顺应性,并促进零废物。 (c)2021 elestvier有限公司保留所有权利。

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