Thermal conductivity modeling of U-Mo/Al dispersion fuel-Reference-Cited by-同舟云学术

Thermal conductivity modeling of U-Mo/Al dispersion fuel

Published:2015-11 Issue: Volume:466 Page:576-582
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Kim Yeon Soo,Cho Byoung Jin^ORCID,Sohn Dong-Seong^ORCID,Park Jong Man

Funder

National Research Foundation of Korea

Ministry of Education, Science and Technology

U.S. Department of Energy, National Nuclear Safety Administration (NNSA), Office of Material Management and Minimization (NA-23) Reactor Conversion Program

Publisher

Elsevier BV

Subject

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

Reference22 articles.

1. USE OF A CENTRIFUGAL ATOMIZATION PROCESS IN THE DEVELOPMENT OF RESEARCH REACTOR FUEL

2. Uranium intermetallic fuels (U–Al, U–Si, U-Mo);Yeon Soo Kim,2012

3. Reaction layer growth and reaction heat of U-Mo/Al dispersion fuels using centrifugally atomized powders;Ryu;J. Nucl. Mater.,2003

4. ANL/RERTR/TM-11;Wiencek,1995

5. Dielectric constant and conductivity of mixtures of isotopic materials;Bruggeman;Ann. Phys.,1935

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