Thermal conductivity calculation of ZrC–ZrO2 pellet from powder metallurgy as the surrogate of UCO kernel fuel

Author:

Dewi Ariyani Kusuma,Yamaguchi Souichirou,Onitzuka Takashi,Uno Masayoshi

Funder

Nuclear Fuel Industries, Ltd

Publisher

Elsevier BV

Subject

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

Reference35 articles.

1. Fabrication of uranium oxycarbide kernels and compacts for HTR fuel;Phillips;Nucl. Eng. Des.,2012

2. High Temperature Gas Cooled Reactor Fuels and Materials;IAEA-TECDOC-1645,2010

3. Kinetic study of the UO2/C interaction by high-temperature mass spectrometry;Gossé;Nucl. Eng. Des.,2008

4. Fabrication process and product quality improvements in advanced gas reactor UCO kernels;Barnes,2008

5. Fabrication of uranium oxycarbide kernels for HTR fuel;Nagley,2010

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