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Recovery of Zirconium from Zircaloys Using a Hydrochlorination Process

机译:利用氢氯化工艺回收锆锆的锆

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摘要

For several decades, extensive research has been performed on the recovery and purification of zirconium from spent nuclear fuel cladding using a variety of chlorination reaction processes. After the reaction between fuel cladding and chlorine gas, zirconium tetrachloride is separated from other chloride species based on their boiling/sublimation points; however, the presence of iron and niobium chloride impurities limits the efficiency of these processes. In this work, chlorination products of Zr, Fe, and Nb mixtures were analyzed by thermogravimetric analysis, and the results suggest that Fe impurities cannot be removed via chlorination alone. Purification of zirconium from Zircaloy-2, Zircaloy-4, and a Zr-Nb alloy was performed via hydrochlorination using a sealed tube reaction system. The purity of the final ZrCl_4 products is higher than 99.99% after successful removal of Fe and Nb.
机译:几十年来,通过各种氯化反应方法对废核燃料包层的锆的回收和纯化进行了广泛的研究。在燃料包层和氯气之间的反应后,四氯化锆基于其沸腾/升华点与其他氯化物物种分离;然而,铁和氯化铌杂质的存在限制了这些方法的效率。在这项工作中,通过热重分析分析Zr,Fe和Nb混合物的氯化产物,结果表明,不能单独通过氯化除去Fe杂质。通过使用密封的管反应系统通过氢氯化氢化锆锆的氧化锆和Zr-Nb合金。成功除去Fe和Nb后,最终ZrCl_4产品的纯度高于99.99%。

著录项

  • 来源
    《Nuclear Technology》 |2021年第2期|263-269|共7页
  • 作者单位

    University of Nevada Las Vegas Department of Chemistry and Biochemistry 4505 South Maryland Parkway Las Vegas Nevada 89154;

    Paciflc Northwest National Laboratory 902 Battelle Boulevard Richland Washington 99352;

    University of Nevada Las Vegas Department of Chemistry and Biochemistry 4505 South Maryland Parkway Las Vegas Nevada 89154;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    Zirconium; Zircaloy; hydrochlorination; thermogravimetric analysis;

    机译:锆;锆石;氢氯化;热重分析;

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