首页> 外文会议>Diffusion in solids and liquids VI >Characterization of Interaction Layer in U-Mo-X (X = Nb, Zr) and U-Nb-Zr vs. Al Diffusion Couples Annealed at 600℃ for 10 Hours
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Characterization of Interaction Layer in U-Mo-X (X = Nb, Zr) and U-Nb-Zr vs. Al Diffusion Couples Annealed at 600℃ for 10 Hours

机译:U-Mo-X(X = Nb,Zr)和U-Nb-Zr与Al扩散对在600℃下退火10小时的相互作用层的表征

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摘要

U-Mo has thus far proven to be one of the most feasible metallic fuel alloys for use in research and test reactors due to its high density and stability during irradiation. However, an adverse diffusional interaction can occur between the fuel alloy and the Al based matrix. This forms an interaction layer (IL) that has undesirable thermal properties and irradiation behavior leading to accelerated swelling and reduced fuel efficiency. This study focused on the effects of ternary alloying additions on the formation of IL between U based alloys and Al. Diffusion couples of U-8Mo-3Nb, U-7Mo-6Zr, and U-10Nb-4Zr (wt.%) vs. pure Al were assembled and annealed at 600℃ for 10 hours. Both thickness and phase constituent analyses were performed via electron microscopy. The major phase constituent of the IL was determined to be the UAl_3 intermetallic compound. The Nb and Zr alloying additions did not reduce growth rate of IL (1.3~1.4 μm/sec~(1/2)) as compared to couples made between binary U-Mo and Al (0.9-1.8 μm/sec~(1/2)).
机译:迄今为止,由于铀钼的高密度和辐射稳定性,它已被证明是用于研究和测试反应堆的最可行的金属燃料合金之一。然而,在燃料合金和Al基基体之间可能发生不利的扩散相互作用。这形成相互作用层(IL),该相互作用层具有不期望的热性能和辐照行为,从而导致膨胀加速和燃料效率降低。这项研究集中于三元合金添加对U基合金与Al之间的IL形成的影响。组装了U-8Mo-3Nb,U-7Mo-6Zr和U-10Nb-4Zr(重量%)相对于纯Al的扩散对,并在600℃下退火10小时。厚度和相组成分析均通过电子显微镜进行。 IL的主要相成分被确定为UAl_3金属间化合物。与二元U-Mo和Al的偶合(0.9-1.8μm/ sec〜(1 /)相比,Nb和Zr合金添加不会降低IL的生长速率(1.3〜1.4μm/ sec〜(1/2))。 2))。

著录项

  • 来源
    《Diffusion in solids and liquids VI》|2010年|p.1055-1062|共8页
  • 会议地点 Paris(FR);Paris(FR)
  • 作者单位

    Advanced Materials Processing and Analysis Center Department of Mechanical, Materials, and Aerospace Engineering University of Central Florida 4000 Central Florida Blvd., Orlando, FL 32816;

    Advanced Materials Processing and Analysis Center Department of Mechanical, Materials, and Aerospace Engineering University of Central Florida 4000 Central Florida Blvd., Orlando, FL 32816;

    Nuclear Fuels and Materials Division Idaho National Laboratory P.O. Box 1625, Scoville, ID, 83415;

    Advanced Materials Processing and Analysis Center Department of Mechanical, Materials, and Aerospace Engineering University of Central Florida 4000 Central Florida Blvd., Orlando, FL 32816;

  • 会议组织
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 工程材料一般性问题;
  • 关键词

    fuel-cladding interaction; metallic nuclear fuels; uranium alloys; diffusion;

    机译:燃料-包层相互作用金属核燃料;铀合金扩散;

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