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Retention of cesium and strontium by uranophane, Ca (UO_2)_2(SiO_3OH)_2-5H_2O

机译:铀no烷,Ca(UO_2)_2(SiO_3OH)_2-5H_2O对铯和锶的保留

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摘要

This work determines the capacity of uranophane, one of the long-term uranyl secondary solid phases formed on the spent nuclear fuel (SNF), to retain radionuclides (cesium and strontium) released during the dissolution of the SNF. Sorption was fast in both cases, and uranophane had a high sorption capacity for both radionuclides (maximum sorption capacities of 1.53·10−5 mol m-2for cesium and 3.45·10−3 mol m−2for strontium). The high sorption capacity of uranophane highlights the importance of the formation of uranyl silicates as secondary phases during the SNF dissolution, especially in retaining the release of radionuclides not retarded by other mechanisms such as precipitation.
机译:这项工作确定了在废核燃料(SNF)上形成的长期铀酰二级固相之一的铀酰phane保留在SNF溶解过程中释放的放射性核素(铯和锶)的能力。在这两种情况下,吸附速度都很快,而铀脲烷对两种放射性核素都具有很高的吸附能力(铯的最大吸附能力为1.53·10-5 mol·m-2,锶的最大吸附能力为3.45·10-3-3 mol·m-2。铀酰脲的高吸附能力突出了在SNF溶解过程中形成铀酰硅酸盐作为次生相的重要性,特别是在保留不受其他机制(例如沉淀)阻碍的放射性核素释放方面。

著录项

  • 来源
    《Journal of Hazardous Materials》 |2018年第5期|431-435|共5页
  • 作者单位

    Department of Chemical Engineering, Barcelona Research Center in Multiscale Science and Engineering, Universitat Politècnica de Catalunya;

    Department of Chemical Engineering, Barcelona Research Center in Multiscale Science and Engineering, Universitat Politècnica de Catalunya;

    Department of Chemical Engineering, Barcelona Research Center in Multiscale Science and Engineering, Universitat Politècnica de Catalunya;

    Department of Chemical Engineering, Barcelona Research Center in Multiscale Science and Engineering, Universitat Politècnica de Catalunya,Fundació CTM Centre Tecnològic;

  • 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);美国《化学文摘》(CA);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    Uranophane; Strontium; Cesium; Sorption; Spent nuclear fuel;

    机译:天王星;锶;铯;吸附;乏核燃料;

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