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Radiation and thermal effects on zeolites, smectites and crystalline silicotitanates.

机译:对沸石,绿土和结晶硅铝酸盐的辐射和热效应。

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摘要

Long-term radiation and thermal effects on materials in the near-field of a nuclear waste repository have been evaluated using accelerated laboratory experiments by energetic electron or ion beam irradiations. The materials studied include: zeolites, smectites, and crystalline silicotitanates (CST).; In situ transmission electron microscopy (TEM) during irradiation by 200 keV electrons has shown that all of the studied materials are susceptible to radiation-induced amorphization. At room temperature, complete amorphization was observed after ionizing doses of 1010∼10 12 Gy or displacement doses of ∼0.1 dpa. The critical amorphization dose increased with temperature for CST. A peak amorphization dose was found at ∼400°C for the smectites. A new experimental approach was developed using a combination of proton irradiation, TEM, and electron microprobe analysis techniques to overcome the difficulties in studying the chemical properties in the radiation-damaged region. A clear correlation between the structural damage and changes in ion-exchange and desorption capacities has been established for zeolite-Y, which maybe useful for predicting the long-term behavior of the near-field materials in a nuclear waste repository. Radiation-induced decrease in the release rate of radionuclides has been observed for the first time in the damaged materials, indicating that the structural damage in near-field materials may be beneficial for retarding the release of radionuclides from geologic disposal repository into biosphere. Possible mechanisms for radiation-induced changes in structure, ion exchange and desorption capacities have been proposed.
机译:通过利用高能电子或离子束辐照进行的加速实验室实验,已经评估了对核废物处置库近场中材料的长期辐射和热效应。研究的材料包括:沸石,绿土和结晶硅钛酸盐(CST)。 200 keV电子照射期间的原位透射电子显微镜(TEM)表明,所有研究的材料都容易受到辐射诱导的非晶化作用。在室温下,电离剂量为10 10 〜10 12 Gy或置换剂量为〜0.1 dpa后,观察到完全非晶化。 CST的临界非晶化剂量随温度增加而增加。蒙脱石的非晶化剂量在约400°C时达到峰值。结合质子辐照,TEM和电子微探针分析技术,开发了一种新的实验方法,以克服研究受辐射损坏区域的化学特性的难题。已经确定了Y型沸石的结构破坏与离子交换和解吸能力变化之间的明确关联,这可能对预测核废料处置库中近场材料的长期行为有用。首次在受损材料中观察到辐射引起的放射性核素释放速率的降低,这表明近场材料的结构破坏可能有利于阻止放射性核素从地质处置库向生物圈的释放。已经提出了辐射诱导的结构变化,离子交换和解吸能力的可能机制。

著录项

  • 作者

    Gu, Binxi.;

  • 作者单位

    University of Michigan.;

  • 授予单位 University of Michigan.;
  • 学科 Engineering Nuclear.
  • 学位 Ph.D.
  • 年度 2001
  • 页码 211 p.
  • 总页数 211
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 原子能技术;
  • 关键词

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