The modeling and simulation of the thermal conductivity of irradiated U-Mo dispersion fuel: Estimation of the thermal conductivity of the interaction layer-Reference-Cited by-同舟云学术

The modeling and simulation of the thermal conductivity of irradiated U-Mo dispersion fuel: Estimation of the thermal conductivity of the interaction layer

Published:2018-11 Issue: Volume:510 Page:199-209
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Mistarihi Qusai M.,Hwang Jun Teak,Ryu Ho Jin^ORCID

Funder

KAIST

National Research Foundation of Korea

Ministry of Science

ICT

Publisher

Elsevier BV

Subject

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

Reference56 articles.

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4. Irradiation behavior of low-enriched U6Fe-Al dispersion fuel elements;Hofman;J. Nucl. Mater.,1987

5. Irradiation behavior of U-Nb-Zr alloy dispersed in aluminum;Meyer;J. Nucl. Mater.,2001

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