首页> 美国政府科技报告 >Fabrication Development of Beryllium-CladnUranium-3.8% Silicon, Uranium-10% Molybdenum,nand Uranium - Uranium Monocarbide Cermets
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Fabrication Development of Beryllium-CladnUranium-3.8% Silicon, Uranium-10% Molybdenum,nand Uranium - Uranium Monocarbide Cermets

机译:铍 - 铀 - 锗-3.8%硅,铀-10%钼,铀 - 铀单碳化物金属陶瓷的制造开发

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摘要

Beryllium was extrusion clad and/or roll clad on uranium-3.87o silicon (epsilon uranium), uranium-10% molybdenum, and uranium-uranium monocarbide cermets containing uranium monocarbide of the order of 58 to 62 /o, with the following results:n(a) Uranium-3.8% siliconnExtrusion cladding, including end sealing, was successful when extrusion temperature was in the range 1650 - 1750 F (898 - 954 G). Below 1650 F extrusion cladding was not successful.nRoll cladding was not successful at 1600 - 1750°F (872 - 954°C) but results indicate further development should be undertaken at the upper end of this temperature range.

著录项

  • 作者

    J. Greenspan;

  • 作者单位
  • 年度 1960
  • 页码 1-72
  • 总页数 72
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 工业技术;
  • 关键词

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