期刊论文详细信息
JOURNAL OF NUCLEAR MATERIALS 卷:496
Thermal properties of U-7Mo/Al dispersion fuel
Article
Cho, Tae Won1  Kim, Yeon Soo2  Park, Jong Man3  Lee, Kyu Hong3  Kim, Sunghwan3  Lee, Chong-Tak3  Yang, Jae Ho3  Oh, Jang Soo3  Won, Ju-Jin3  Sohn, Dong-Seong1 
[1] Ulsan Natl Inst Sci & Technol, Dept Nucl Engn, 50 UNIST Gil, Ulsan 689798, South Korea
[2] Argonne Natl Lab, 9700 S Cass Ave, Argonne, IL 60439 USA
[3] Korea Atom Energy Res Inst, 989-111 Daedeok Daero, Daejeon 305353, South Korea
关键词: U-Mo/Al dispersion fuel;    Si addition in matrix;    Thermal diffusivity;    Heat capacity;    Density;    Uranium loading;    Thermal conductivity;    Measured data;   
DOI  :  10.1016/j.jnucmat.2017.09.039
来源: Elsevier
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【 摘 要 】

The thermal diffusivity and heat capacity of U-7Mo/Al and U-7Mo/Al-5Si as functions of U-Mo fuel volume fraction and temperature were measured. The density of the sample was measured at room temperature and estimated using thermal expansion data at elevated temperatures. Using the measured data, the thermal conductivity was obtained as a function of U-Mo volume fraction and temperature. The thermal conductivity of U-7Mo/Al-5Si was found to be lower than that of U-7Mo/Al because of the Si addition to the Al. Due to a lower porosity and reduced interaction between U-Mo and Al in the sample, the thermal conductivity data reported in the present study were higher than those in the literature. The present data were found to be in agreement with the predictions of theoretical models. (C) 2017 Elsevier B.V. All rights reserved.

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