Thermal conductivity of (U,Pu,Np)O2 solid solutions-Reference-Cited by-同舟云学术

Thermal conductivity of (U,Pu,Np)O2 solid solutions

Published:2009-05 Issue:1 Volume:389 Page:179-185
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Morimoto Kyoichi,Kato Masato,Ogasawara Masahiro,Kashimura Motoaki

Publisher

Elsevier BV

Subject

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

Reference25 articles.

1. R&D activities based on fast reactor cycle technologies for transmutation of TRU and LLFP by JNC

2. The thermal conductivity of ovides of uranium, neptunium and americium at elevated temperatures

3. M. Katayama, J. Adachi, K. Kurosaki, M. Uno, S. Miwa, M. Osaka, K. Tanaka, S. Yamanaka, in: Mater. Res. Soc. Symp. Proc., vol. 1043E, Warrendale, PA, 2007, 1043-T09-06.

4. Thermal conductivity of neptunium dioxide

Cited by 24 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. Enthalpy measurement on (U1−xPux)O2 (x = 0, 0.18, 0.45, and 1) and analysis of heat capacity;Journal of Nuclear Materials;2024-09

2. Thermal conductivity measurement of uranium–plutonium mixed oxide doped with Nd/Sm as simulated fission products;Journal of Nuclear Materials;2024-01

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

4. Analytical evaluation of isochoric and isobaric heat capacities for actinide dioxide nuclear fuels;Pramana;2023-05-16

5. Measurements of thermal conductivity for near stoichiometric (U0.7-zPu0.3Amz)O2 (z = 0.05, 0.10, and 0.15);Nuclear Materials and Energy;2022-06