Extraction of uranium from tailings by sulfuric acid leaching with oxidants
作者：
Huang, Jing;Li, Mi* ;Zhang, Xiaowen;Huang, Chunmei;Wu, Xiaoyan
期刊：
IOP Conference Series: Earth and Environmental Science ,2017年69(1) ISSN：1755-1307
通讯作者：
Li, Mi
作者机构：
[Li, Mi; Huang, Jing; Zhang, Xiaowen; Huang, Chunmei; Wu, Xiaoyan] Univ South China, Sch Environm Protect & Safety Engn, Hengyang 421001, Peoples R China.;[Li, Mi; Zhang, Xiaowen] Univ South China, Key Lab Radioact Waste Treatment & Disposal, Hengyang 421001, Peoples R China.
通讯机构：
[Li, Mi] U;Univ South China, Sch Environm Protect & Safety Engn, Hengyang 421001, Peoples R China.;Univ South China, Key Lab Radioact Waste Treatment & Disposal, Hengyang 421001, Peoples R China.
会议名称：
3rd International Conference on Advances in Energy, Environment and Chemical Engineering (AEECE)
会议时间：
MAY 26-28, 2017
会议地点：
Chengdu, PEOPLES R CHINA
会议主办单位：
[Huang, Jing;Li, Mi;Zhang, Xiaowen;Huang, Chunmei;Wu, Xiaoyan] Univ South China, Sch Environm Protect & Safety Engn, Hengyang 421001, Peoples R China.^[Li, Mi;Zhang, Xiaowen] Univ South China, Key Lab Radioact Waste Treatment & Disposal, Hengyang 421001, Peoples R China.
会议论文集名称：
IOP Conference Series-Earth and Environmental Science
摘要：
Recovery of uranium have been performed by leaching uranium-containing tailings in sulfuric acid system with the assistance of HF, HClO4, H2O2 and MnO2. The effect of reagent dosage, sulfuric acid concentration, Liquid/solid ratio, reaction temperature and particle size on the leaching of uranium were investigated. The results show that addiction of HF, HClO4, H2O2 and MnO2 significantly increased the extraction of uranium under 1M sulphuric acid condition and under the optimum reaction conditions a dissolution fraction of 85% by HClO4, 90% by HF, 95% by H2O2 can be reached respectively. The variation of technological mineralogy properites of tailings during leaching process show that the assistants can break gangue effectively. These observations suggest that optimum oxidants could potentially influence the extraction of uranium from tailings even under dilute acid condition. ©Published under licence by IOP Publishing Ltd.
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Kinetics of Uranium Extraction from Uranium Tailings by Oxidative Leaching
作者：
Zhang, Biao;Li, Mi* ;Zhang, Xiaowen;Huang, Jing
期刊：
JOM ,2016年68(7):1990-2001 ISSN：1047-4838
通讯作者：
Li, Mi
作者机构：
[Zhang, Biao; Li, Mi; Huang, Jing; Zhang, Xiaowen] Univ South China, Sch Environm Protect & Safety Engn, Hengyang 421001, Peoples R China.;[Li, Mi; Zhang, Xiaowen] Univ South China, Key Lab Radioact Waste Treatment & Disposal, Hengyang 421001, Peoples R China.
通讯机构：
[Li, Mi] U;Univ South China, Sch Environm Protect & Safety Engn, Hengyang 421001, Peoples R China.;Univ South China, Key Lab Radioact Waste Treatment & Disposal, Hengyang 421001, Peoples R China.
关键词：
Uranium;Sulfuric Acid Solution;Uranium Concentration;Uranium Oxide;Shrink Core Model
摘要：
Extraction of uranium from uranium tailings by oxidative leaching with hydrogen peroxide (H<inf>2</inf>O<inf>2</inf>) was studied. The effects of various extraction factors were investigated to optimize the dissolution conditions, as well as to determine the leaching kinetic parameters. The behavior of H<inf>2</inf>O<inf>2</inf>in the leaching process was determined through scanning electron microscopy-energy dispersive x-ray spectroscopy (SEM-EDX) and x-ray diffraction analysis of leaching residues. Results suggest that H<inf>2</inf>O<inf>2</inf>can significantly improve uranium extraction by decomposing the complex gangue structures in uranium tailings and by enhancing the reaction rate between uranium phases and the leaching agent. The extraction kinetics expression was changed from 1 − 3(1 − α)<sup>2/3</sup> + 2(1 − α) = K<inf>0</inf>(H<inf>2</inf>SO<inf>4</inf>)<sup>−0.14903</sup>(S/L)<sup>−1.80435</sup>(R<inf>o</inf>)<sup>0.20023</sup>e<sup>−1670.93/T</sup>t (t ≥ 5) to 1 − 3(1 − α)<sup>2/3</sup> + 2(1 − α) = K<inf>0</inf>(H<inf>2</inf>SO<inf>4</inf>)<sup>0.01382</sup>(S/L)<sup>−1.83275</sup>(R<inf>o</inf>)<sup>0.25763</sup>e<sup>−1654.59/T</sup>t (t ≥ 5) by the addition of H<inf>2</inf>O<inf>2</inf>in the leaching process. The use of H<inf>2</inf>O<inf>2</inf>in uranium leaching may help in extracting uranium more efficiently and rapidly from low-uranium-containing ores or tailings. ©2016, The Minerals, Metals & Materials Society.
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英文
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采用HF和HClO_4从铀尾矿中浸出铀的试验研究
作者：
李密;黄婧;戴士祥;张晓文;张彪;...
期刊：
中国矿业大学学报 ,2016年45(3):639-645 ISSN：1000-1964
通讯作者：
Li, Mi(enemy_1983@163.com)
作者机构：
[李密; 戴士祥; 黄婧; 张晓文; 张彪] School of Environment Protection and Safety Engineering, University of South China, Hengyang, Hunan, 421001, China;[丁德馨] Key Discipline Laboratory for National Defense for Biotechnology in Uranium Mining and Hydrometallurgy, University of South China, Hengyang, Hunan, 421001, China;[李密; 张晓文] Key Laboratory of Radioactive Waste Treatment and Disposal, University of South China, Hengyang, Hunan, 421001, China
通讯机构：
School of Environment Protection and Safety Engineering, University of South China, Hengyang, Hunan, China
关键词：
铀尾矿;浸出;强化机理;脉石
摘要：
为了从低品位铀尾矿中回收铀资源,在详细分析了铀尾矿工艺矿物学性质的基础上,提出了以硫酸为浸出剂,HF和HClO_4为强化剂的氧化强化浸铀工艺,研究了工艺参数对铀浸出的影响,并通过X射线衍射仪、激光粒度仪及扫描电镜等手段分析铀尾矿浸出过程中的物相、粒度及形貌特征变化,揭示了HF和HClO_4对铀尾矿浸出的强化作用机理.研究结果表明:HF可分解硅酸盐类矿物结构,而HClO_4可对脉石颗粒表面造成"溶蚀",二者均可促进脉石颗粒与铀的解离,但HClO_4的作用效果低于HF.当浸出温度为50 ℃,硫酸浓度为1.5 mol/L,浸出时间为80 min,液固质量比为12时,HF和HClO_4对铀的浸出率分别为96%和78%.
语种：
中文
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Investigation of gamma ray shielding efficiency and mechanical performances of concrete shields containing bismuth oxide as an environmentally friendly additive
作者：
Yao, Ya;Zhang, Xiaowen* ;Li, Mi;Yang, Rong;Jiang, Tianjiao;...
期刊：
Radiation Physics and Chemistry ,2016年127:188-193 ISSN：0969-806X
通讯作者：
Zhang, Xiaowen
作者机构：
[Yao, Ya; Yang, Rong; Jiang, Tianjiao] Univ South China, Sch Environm Protect & Safety Engn, Hengyang 42100, Peoples R China.;[Li, Mi; Lv, Junwen; Zhang, Xiaowen] Univ South China, Key Lab Radioact Waste Treatment & Disposal, Hengyang 421001, Hunan, Peoples R China.
通讯机构：
[Zhang, Xiaowen] U;Univ South China, Key Lab Radioact Waste Treatment & Disposal, Hengyang 421001, Hunan, Peoples R China.
关键词：
Bismuth oxide;Compressive strength;Concrete;Lead oxide;Linear attenuation coefficient
摘要：
Concrete has a proven ability to attenuate gamma rays and neutrons without compromising structural property;therefore, it is widely used as the primary shielding material in many nuclear facilities. Recently, there is a tendency toward using various additives to enhance the shielding properties of these concrete mixtures. However, most of these additives being used either pose hygiene hazards or require special handling processes. It would be ideal if environmentally friendly additives were available for use. The bismuth oxide (Bi<inf>2</inf>O<inf>3</inf>) additive shows promise in various shielding applications due to its proven radiation attenuation ability and environmentally friendly nature. To the best of our knowledge, however, Bi<inf>2</inf>O<inf>3</inf>has never been used in concrete mixtures. Therefore, for this research, we fabricated the Bi<inf>2</inf>O<inf>3</inf>-based concrete mixtures by adding Bi<inf>2</inf>O<inf>3</inf>powder in the ordinary concrete mixture. Concrete mixtures with lead oxide (PbO) additives were used for comparison. Radiation shielding parameters like the linear attenuation coefficients (LAC) of all these concrete mixtures showing the effects of the Bi<inf>2</inf>O<inf>3</inf>additions are presented. The mechanical performances of concrete mixtures incorporated with Bi<inf>2</inf>O<inf>3</inf>additive were also investigated. It suggested that the concrete mixture containing 25% Bi<inf>2</inf>O<inf>3</inf>powder (B5 in this study) provided the best shielding capacity and mechanical performance among other mixes. It has a significant potential for application as a structural concrete where radiological protection capability is required. ©2016 Elsevier Ltd
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英文
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