退火法制备TiO2/Ti电极及其对有机含铀废水的电化学净化

Preparation of TiO2/Ti Electrode by Annealing Method and Its Electrochemical Purification of Organic Uranium-containing Wastewater

  • 摘要: 高温气冷堆燃料元件生产过程中会产生相当量的偏碱性含铀废水,其中还含有一定浓度的尿素、聚乙烯醇、四氢糠醇等有机物。为实现有机含铀废水的净化,本研究针对这种废水开展铀去除研究。首先通过对Ti片进行680 ℃退火处理,制备了TiO2/Ti电极,然后配制有机含铀模拟溶液,采用电化学法开展模拟溶液中铀的去除研究,探索了碳酸根浓度、pH、铀初始浓度、时间、电压等因素对铀去除率的影响,并推测了过程的反应机理。X射线光电子谱(XPS)、扫描电子显微镜(SEM)、电子能谱(EDS)和X射线衍射(XRD)分析表明,通过退火处理合成的TiO2/Ti电极表面被颗粒状金红石相TiO2覆盖,说明通过退火法能成功制备TiO2/Ti电极。电化学法去除模拟溶液(pH=9)中铀的最优条件为:碳酸钠浓度0.01 mol/L、电压10 V、时间5 h,此条件下铀去除率达95.43%。0.01 mol/L碳酸钠溶液中,铀的还原电位为−0.99 V (vs SCE),其还原过程为一步单电子过程,U(Ⅵ)得到1个电子还原为U(Ⅴ),再歧化为U(Ⅳ)和U(Ⅵ),铀是以UO2和U2O5的形态沉积在电极表面。在4种共存物中,硝酸铵、尿素和聚乙烯醇对铀去除有明显的抑制,而四氢糠醇则没有明显影响。它们共同存在时,在10 V条件下,铀去除率下降至36.75%,但通过提升电压至15 V,铀去除率上升至85.99%。本文所制备TiO2/Ti电极的重复利用性良好,重复使用8次后,铀去除率仍能达到90%以上,每次重复使用,铀的回收率基本能达90%以上。

     

    Abstract: A considerable amount of waste solution of low uranium concentration is generated during the fuel production for high-temperature gas-cooled reactors, it contains high concentration of urea and some organics including polyvinyl and tetrahydrofurfuryl alcohol. In order to remove uranium from the low-level wastewate using TiO2/Ti electrochemical method, the electrode was prepared by annealing Ti flakes at 680 ℃ for 2 h, the effect on uranium removal efficiency of varying parameters, such as the concentration of sodium carbonate, pH of the solution, time, the concentration of uranium, and voltage of the working electrode, and the mechanism for removing uranium was proposed. The results from scanning electron microscopy (SEM), X-ray photoelectron spectroscopy (XPS) and X-ray diffractometer (XRD) indicate that a layer of nanoscale oxide particles is formed on the surface of the TiO2/Ti electrode during the annealing treatment. Under optimized conditions, over 95.43% of uranium can be removed from the solution of 0.01 mol/L sodium carbonate within 5 h under electrode voltage of 10 V. Cyclic voltammetry tests show that only one pair of redox peaks for uranium at −0.99 V and −0.48 V (vs SCE) exist in the potential range of −2 V to 0.5 V (vs SCE), and square wave voltammetry tests show that only one electron transfer involves in the process of uranium deposition on the electrode, indicating that the reduction process of uranium is going through two steps, first U(Ⅵ) gets an electron to be reduced to U(Ⅴ) controlled by diffusion, then U(Ⅴ) disproportionates to U(Ⅳ) and U(Ⅵ). The results of reduction product characterization show that uranium is deposited on the electrode surface in the form of mixed UO2 and U2O5. The experimental results of uranium removal show that the electrodeposition rate of uranium gradually slows down after 5 h. With additional working time, for example, at 10 h, the removal rate of uranium can reach 98.52%. Uranium removal rate is above 90% in the solution pH=3-11 range and in the initial uranium concentration range of 10-500 mg/L. Among the organic substances, urea and polyvinyl significantly inhibit uranium removal, while tetrahydrofurfuryl alcohol does not. In addition, uranium removal rate decreases rapidly with increasing ammonium nitrate concentration.

     

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