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首页> 外文期刊>Journal of Materials Science >Crystallization study of (TiO2, ZrO2)-rich SiO2-Al2O3-CaO glasses Part I Preparation and characterization of zirconolite-based glass-ceramics
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Crystallization study of (TiO2, ZrO2)-rich SiO2-Al2O3-CaO glasses Part I Preparation and characterization of zirconolite-based glass-ceramics

机译:富含(TiO2 ,ZrO2 )的SiO2 -Al2 O3 -CaO玻璃的结晶研究第一部分锆石基微晶玻璃的制备与表征

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摘要

Nuclear power reactors generate long-lived radionuclides such as minor actinides (Np, Am, Cm) which are mainly responsible for the long term radiotoxicity of high level nuclear wastes obtained after reprocessing of nuclear spent fuel. Specific highly durable matrices such as glass-ceramics appear as good candidates for the immobilization of minor actinides. This work concerns the synthesis and the characterization of zirconolite (CaZrTi2O7) based glass-ceramics prepared by controlled devitrification of (TiO2, ZrO2)-rich SiO2-Al2O3-CaO parent glasses for which neodymium was selected to simulate the radioactive trivalent minor actinides. The present study reports the effect of increasing TiO2, ZrO2 and CaO amounts in glass composition on the structure and the composition of the zirconolite crystals (formed as the only crystalline phase in the bulk of the glass), on their nucleation rate I(Z) and on the volume proportion of crystalline phase V of the glass-ceramics. It appears that I(Z) and V strongly increase when the parent glass composition changes. Neodymium electron spin resonance (ESR) shows that the total amount of Nd3+ ions incorporated in the zirconolite phase increases with TiO2, ZrO2 and CaO amounts in parent glass composition.
机译:核动力反应堆会产生长寿命的放射性核素,例如次act系元素(Np,Am,Cm),这主要是对核废燃料进行后处理后获得的高含量核废料的长期放射毒性。特定的高耐用性基质(例如玻璃陶瓷)似乎是固定次act系元素的良好候选者。这项工作涉及通过富含(TiO2 ,ZrO2 )的SiO2 失透制备的锆石(CaZrTi2 O7 )基玻璃陶瓷的合成和表征。 > -Al2 O3 -CaO母玻璃,选择钕来模拟放射性三价微量minor系元素。本研究报告了增加玻璃成分中TiO2 ,ZrO2 和CaO的量对锆石晶体(形成为玻璃体中唯一的结晶相)的结构和组成的影响,它们的成核速率I(Z)和玻璃陶瓷的结晶相V的体积比例。当母体玻璃组成改变时,I(Z)和V似乎大大增加。钕电子自旋共振(ESR)表明,锆母石相中掺入的Nd3 +离子总量随着母体玻璃成分中TiO2,ZrO2和CaO的增加而增加。

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  • 来源
    《Journal of Materials Science》 |2003年第4期|843-852|共10页
  • 作者单位

    Laboratoire de Chimie Appliquée de l'Etat Solide (UMR CNRS 7574) ENSCP;

    Laboratoire de Chimie Appliquée de l'Etat Solide (UMR CNRS 7574) ENSCP;

    Laboratoire de Chimie Appliquée de l'Etat Solide (UMR CNRS 7574) ENSCP;

    Laboratoire de Chimie Appliquée de l'Etat Solide (UMR CNRS 7574) ENSCP;

    Direction de l'Energie Nucléaire Centre de la Vallée du Rhôsne DIEC/SCDV/LEBM Commissariat à l'Énergie Atomique (CEA);

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  • 正文语种 eng
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