Thermal conductivity of near-stoichiometric (U, Pu, Zr)C solid solutions-Reference-Cited by-同舟云学术

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Thermal conductivity of near-stoichiometric (U, Pu, Zr)C solid solutions

Published:1989-10 Issue:1-2 Volume:168 Page:137-143
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Arai Yasuo,Ohmichi Toshihiko,Fukushima Susumu,Handa Muneo

Publisher

Elsevier BV

Subject

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

Reference29 articles.

1. Uranium-Plutonium Carbides as an LMFBR Fuel;Herbst;Los Alamos National Laboratory Report, LA-9259-MS,1982

2. Proc. Conf. on Advanced LMFBR Fuels;Pascard,1977

3. Proc. Int. Conf. on Reliable Fuels for Liquid Metal Reactors;Guerin,1986

4. Thermal Conductivity of Mixed Carbides, Nitrides and Carbonitrides;VanCrarynest;CEA Report, CEA-CONF-1248,1969

Cited by 5 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. C-Pu-U Ternary Phase Diagram Evaluation;MSI Eureka;2019-11-12

2. Zirconium Monocarbide;Ultra-High Temperature Materials II;2019

3. C-Pu-Zr (Carbon-Plutonium-Zirconium);Non-Ferrous Metal Systems. Part 4;2007

4. C-Pu-U (Carbon-Plutonium-Uranium);Non-Ferrous Metal Systems. Part 4;2007

5. Nonoxide Ceramic Nuclear Fuels;Materials Science and Technology;2006-09-15

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