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PRODUCTION AND CHARACTERIZATION OF ZrC-UC INERT MATRIX COMPOSITE FUEL FOR GAS FAST REACTORS

机译:燃气快速反应器用ZrC-UC惰性基质复合燃料的生产与表征

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摘要

Dispersed fuel composites consisting of uranium carbide particles (microspheres) in a zirconium carbide (inert) matrix were fabricated and characterized. Advanced fuels including refractory inert matrix fuels are being considered for gas fast reactors, which can accommodate a variety of feed materials including recycled transuranics that include minor actinides for incineration and high-level waste reduction. The particles for this effort were fabricated by employing a custom built rotating electrode machine. This process employed a uranium carbide electrode manufactured by combustion synthesis of uranium hydride and graphite powders. Two process parameters, namely, arc intensity and rotational speed, were varied to assess their effects on the size of the particles produced. The particles were characterized for microstructure, density, and composition (homogeneity). These particles were mixed with pure zirconium and graphite powders in different matrix to particle volumetric ratios of 90/10, 80/20, and 70/30 and inductively heated to 1850℃ to initiate combustion synthesis to produce composites of zirconium carbide with the embedded uranium carbide particles. The aim was to limit process temperature and in particular process time, bearing in mind the possible future extensions of these processes to minor actinide-bearing fuels and also to avoid any changes in the structural integrity of the particles and large-scale diffusion of uranium into the matrix. The composites were characterized for microstructure, phase composition, density, and porosity distribution. The results are presented.
机译:制备并表征了由碳化锆(惰性)基体中的碳化铀颗粒(微球)组成的分散燃料复合材料。快气反应堆正在考虑使用包括耐火惰性基质燃料在内的先进燃料,该反应堆可容纳多种进料,包括循环的超铀酸,其中包括微量的act系元素,用于焚烧和高水平的废物减少。通过使用定制的旋转电极机来制造用于此目的的颗粒。该方法采用碳化铀电极,该碳化铀电极是通过氢化铀和石墨粉的燃烧合成而制造的。改变两个工艺参数,即电弧强度和旋转速度,以评估它们对产生的颗粒尺寸的影响。表征颗粒的微观结构,密度和组成(均匀性)。将这些颗粒与纯锆和石墨粉末混合,以不同的基质体积比达到90 / 10、80 / 20和70/30,并感应加热至1850℃以引发燃烧合成,从而制备出嵌入了铀的碳化锆复合材料。碳化物颗粒。这样做的目的是限制工艺温度,特别是工艺时间,同时考虑到这些工艺将来可能会扩展到含次act系元素的燃料,并且还要避免颗粒的结构完整性发生任何变化以及铀大量扩散到其中矩阵。对复合材料的微观结构,相组成,密度和孔隙率分布进行了表征。显示结果。

著录项

  • 来源
    《Nuclear Technology》 |2011年第2期|p.200-209|共10页
  • 作者单位

    University of South Carolina, Nuclear Engineering Program Department of Mechanical Engineering, Columbia, South Carolina 29208;

    University of South Carolina, Nuclear Engineering Program Department of Mechanical Engineering, Columbia, South Carolina 29208;

    Savannah River National Laboratory, Aiken, South Carolina 29808;

    University of South Carolina, Nuclear Engineering Program Department of Mechanical Engineering, Columbia, South Carolina 29208;

  • 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

    inert matrix fuels; uranium carbide microspheres; gas fast reactor;

    机译:惰性基质燃料;碳化铀微球气体快堆;

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