Effect of surface characteristics and environmental aging on wetting of Cr-coated Zircaloy-4 accident tolerant fuel cladding material

著录项

• 来源
  《Journal of Nuclear Materials: Materials Aspects of Fission and Fusion 》 |2020年第1期| 共14页
• 作者

  Umretiya Rajnikant V.; Vargas Santiago; Galeano Diana; Mohammadi Reza; Castano Carlos E.; Rojas Jessika V.;

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• 作者单位

  Virginia Commonwealth Univ Dept Mech &

  Nucl Engn Med Coll Virginia Campus Richmond VA 23284 USA;

  Virginia Commonwealth Univ Dept Mech &

  Nucl Engn Med Coll Virginia Campus Richmond VA 23284 USA;

  Virginia Commonwealth Univ Dept Mech &

  Nucl Engn Med Coll Virginia Campus Richmond VA 23284 USA;

  Virginia Commonwealth Univ Dept Mech &

  Nucl Engn Med Coll Virginia Campus Richmond VA 23284 USA;

  Virginia Commonwealth Univ Dept Mech &

  Nucl Engn Med Coll Virginia Campus Richmond VA 23284 USA;

  Virginia Commonwealth Univ Dept Mech &

  Nucl Engn Med Coll Virginia Campus Richmond VA 23284 USA;

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• 原文格式 PDF
• 正文语种 eng
• 中图分类 原子能技术 ;
• 关键词