Measurements of thermal conductivity for near stoichiometric (U0.7-zPu0.3Amz)O2 (z = 0.05, 0.10, and 0.15)

Author:

Yokoyama Keisuke,Watanabe MasashiORCID,Tokoro Daishiro,Sugimoto Masatoshi,Morimoto KyoichiORCID,Kato MasatoORCID,Hino Tetsushi

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,Materials Science (miscellaneous),Nuclear and High Energy Physics

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2. Selection of sodium coolant for fast reactors in the US, France and Japan;Sakamoto;Nucl. Eng. Des.,2013

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4. Restructuring and redistribution of actinides in Am-MOX fuel during the first 24h of irradiation;Tanaka;J. Nucl. Mater.,2013

5. Oxygen potentials of (U0.685Pu0.270Am0.045)O2–x solid solution;Osaka;J. Alloy. Compd.,2005

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1. A science‐based mixed oxide property model for developing advanced oxide nuclear fuels;Journal of the American Ceramic Society;2023-12-17

2. Ionic radii in fluorites;Materialia;2023-12

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