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Distribution of fission products in the homogeneous liquid-liquid extraction of uranium.

机译:裂变产物在均相液-液萃取铀中的分布。

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摘要

The radioactive products from uranium fission constitute a serious health hazard due to the possibility of entry into the food chain and uptake by humans. The processing of spent uranium fuels and the separation of uranium from the fission products and their subsequent safe storage is of great concern to the nuclear industry.;Separation of uranium from fission products by homogeneous liquid-liquid extraction of uranium from one molar nitric acid solution with addition of ferric nitrate as salting-out reagent, into propylene carbonate has been performed. Uranium(VI) was quantitatively extracted into propylene carbonate from an aqueous medium of 0.5 g/l Fe(NO;Precipitation of ferric hydroxide from the initial aqueous phase after extraction of uranium, and also from the aqueous sodium carbonate phase after stripping uranium from the propylene carbonate phase affords efficient decontamination from significant fission products.;The representative fission product elements, molybdenum, strontium, ruthenium, zirconium, and cerium, remained in the aqueous solution after extracting uranium(VI) into propylene carbonate to an extent grater than 97%; i.e., less than three percent of the respective elements were found in the carbonate stripping solution. After the final separation step, the extraction of uranyl ion into propylene carbonate containing dibenzoyl methane, these fission product elements were no longer detectable. Ten percent of the original concentration of iodide was found in the carbonate stripping solution. However, it was removed in the final separation step.;This uranium extraction method can be applied as a practical method for separating uranium from fission products to recover the uranium from spent fuel elements. The capacity of ferric hydroxide for adsorption of fission products and the ability to convert to the somewhat refractory ferric oxide also promises convenience for long term storage.
机译:铀裂变产生的放射性产物由于可能进入食物链和被人类吸收而构成严重的健康危害。核燃料工业非常关注铀废燃料的处理以及裂变产物中铀的分离及其随后的安全存储。通过从一摩尔硝酸溶液中均匀地液-液萃取铀,从裂变产物中分离铀通过添加硝酸铁作为盐析试剂,已经进行了碳酸亚丙酯的制备。从0.5 g / l Fe(NO;)的水介质中将铀(VI)定量萃取到碳酸亚丙酯中;从铀萃取后从初始水相中沉淀氢氧化铁,以及从铀中汽提铀后从碳酸钠水相中沉淀出来。碳酸亚丙酯相可对大量裂变产物提供有效的净化作用;将铀(VI)萃取到碳酸亚丙酯中的程度大于97%时,代表性的裂变产物元素(钼,锶,钌,锆和铈)保留在水溶液中;即在碳酸盐汽提液中发现的元素少于百分之三,在最后的分离步骤之后,将铀酰离子萃取到含有二苯甲酰甲烷的碳酸亚丙酯中,这些裂变产物元素不再被检测到。在碳酸盐汽提液中发现了碘的原始浓度,但是在在最终分离步骤中;该铀提取方法可以用作从裂变产物中分离铀以从乏燃料元素中回收铀的实用方法。氢氧化铁吸附裂变产物的能力和转化为难熔的三氧化二铁的能力也为长期储存提供了便利。

著录项

  • 作者

    Xu, Jizhang.;

  • 作者单位

    City University of New York.;

  • 授予单位 City University of New York.;
  • 学科 Chemistry Analytical.;Chemistry Nuclear.
  • 学位 Ph.D.
  • 年度 1988
  • 页码 136 p.
  • 总页数 136
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

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