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Alternative Anodes for the Electrolytic Reduction of Uranium Dioxide.

机译:电解还原二氧化铀的替代阳极。

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摘要

Reprocessing of spent nuclear fuel is an essential step in closing the nuclear fuel cycle. In order to consume current stockpiles, ceramic uranium dioxide spent nuclear fuel will be subjected to an electrolytic reduction process. The current reduction process employs a platinum anode and a stainless steel alloy 316 cathode in a molten salt bath consisting of LiCl-2wt% Li 2O and occurs at 700°C. A major shortcoming of the existing process is the degradation of the platinum anode under the severely oxidizing conditions encountered during electrolytic reduction. This work investigates alternative anode materials for the electrolytic reduction of uranium oxide.;The high temperature and extreme oxidizing conditions encountered in these studies necessitated a unique set of design constraints on the system. Thus, a customized experimental apparatus was designed and constructed. The electrochemical experiments were performed in an electrochemical reactor placed inside a furnace. This entire setup was housed inside a glove box, in order to maintain an inert atmosphere.;This study investigates alternative anode materials through accelerated corrosion testing. Surface morphology was studied using scanning electron microscopy. Surface chemistry was characterized using energy dispersive spectroscopy and Raman spectroscopy. Electrochemical behavior of candidate materials was evaluated using potentiodynamic polarization characteristics. After narrowing the number of candidate electrode materials, ferrous stainless steel alloy 316, nickel based Inconel 718 and elemental tungsten were chosen for further investigation. Of these materials only tungsten was found to be sufficiently stable at the anodic potential required for electrolysis of uranium dioxide in molten salt. The tungsten anode and stainless steel alloy 316 cathode electrode system was studied at the required reduction potential for UO2 with varying lithium oxide concentrations. Electrochemical impedance spectroscopy showed mixed (kinetic and diffusion) control and an overall low impedance due to extreme corrosion.;It was observed that tungsten is sufficiently stable in LiCl - 2wt% Li 2O at 700°C at the required anodic potential for the reduction of uranium oxide. This study identifies tungsten to be a superior anode material to platinum for the electrolytic reduction of uranium oxide, both in terms of superior corrosion behavior and reduced cost, and thus recommends that tungsten be further investigated as an alternative anode for the electrolytic reduction of uranium dioxide.
机译:乏核燃料的后处理是关闭核燃料循环的必不可少的步骤。为了消耗当前的库存,将对陶瓷二氧化铀废核燃料进行电解还原处理。电流还原方法在由LiCl-2wt%Li 2O组成的熔融盐浴中使用铂阳极和不锈钢316不锈钢阴极,发生在700°C。现有方法的主要缺点是在电解还原过程中遇到的严重氧化条件下铂阳极的降解。这项工作研究了用于电解还原铀氧化物的替代阳极材料。这些研究中遇到的高温和极端氧化条件对系统有一套独特的设计约束。因此,设计和构造了定制的实验设备。电化学实验在置于炉内的电化学反应器中进行。为了保持惰性气氛,整个装置都放置在手套箱内。本研究通过加速腐蚀测试研究了替代阳极材料。使用扫描电子显微镜研究了表面形态。使用能谱仪和拉曼光谱仪对表面化学进行了表征。使用电位动力学极化特性评估候选材料的电化学行为。在缩小候选电极材料的数量之后,选择了黑色不锈钢合金316,镍基Inconel 718和元素钨进行进一步研究。在这些材料中,仅发现钨在电解熔融盐中的二氧化铀所需的阳极电势下足够稳定。研究了钨阳极和不锈钢合金316阴极电极系统在不同的氧化锂浓度下所需的UO2还原电位。电化学阻抗谱显示混合(动力学和扩散)控制以及由于极度腐蚀而导致的总体低阻抗。;已观察到,钨在LiCl-2wt%Li 2O中在700°C下在所需的阳极电势下足够稳定,可以还原氧化铀。这项研究表明,就优异的腐蚀性能和降低的成本而言,钨在电解还原铀氧化物方面是铂的优良阳极材料,因此建议进一步研究钨作为电解还原二氧化铀的替代阳极。 。

著录项

  • 作者

    Merwin, Augustus.;

  • 作者单位

    University of Nevada, Reno.;

  • 授予单位 University of Nevada, Reno.;
  • 学科 Engineering Nuclear.;Engineering Materials Science.
  • 学位 M.S.
  • 年度 2012
  • 页码 93 p.
  • 总页数 93
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

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