Fabrication method and thermal conductivity assessment of molybdenum-precipitated uranium dioxide pellets-Reference-Cited by-同舟云学术

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Fabrication method and thermal conductivity assessment of molybdenum-precipitated uranium dioxide pellets

Published:2006-06 Issue:1-3 Volume:352 Page:151-156
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Kim Si-Hyung,Joung Chang-Young,Kim Han-Soo,Lee Young-Woo,Ryu Ho-Jin,Sohn Dong-Seong,Kim Dong-Joo

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference14 articles.

1. Thermal conductivity correlation for uranium nitride fuel between 10 and 1923 K

2. Uranium carbide: Thermal diffusivity, thermal conductivity and spectral emissivity at high temperatures

3. J.H. Yang, K.W. Song, K.S. Kim, Y.H. Jung, in: Proc. Korean Nucl. Soc. Autumn Meeting, October 2004.

4. UO2-cermets with idealized structure by particle coating and isostatic hot pressing

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