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Sohn, Dong-Seong
Innovative Nuclear FUEL(INFUEL)
Research Interests
  • Nuclear fuel design
  • Nuclear fuel
  • Nuclear system
  • Performance analysis

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Thermal conductivities of actinides (U, Pu, Np, Cm, Am) and uranium-alloys (U-Zr, U-Pu-Zr and U-Pu-TRU-Zr)

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Title
Thermal conductivities of actinides (U, Pu, Np, Cm, Am) and uranium-alloys (U-Zr, U-Pu-Zr and U-Pu-TRU-Zr)
Author
Kim, Yeon SooCho, Tae WonSohn, Dong-Seong
Issue Date
2014-02
Publisher
ELSEVIER SCIENCE BV
Citation
JOURNAL OF NUCLEAR MATERIALS, v.445, no.1-3, pp.272 - 280
Abstract
The thermal conductivity correlations of actinides (U, Pu, Np, Cm, Am) and alloys of U-Zr, U-Pu-Zr and U-Pu-TRU-Zr were developed for the use in TRU burning reactors as a function of temperature and alloy composition, using the available data in the literature and extrapolating information obtained in the literature. Because of the scarcity in the measured data for thermal conductivities of TRU elements in the literature, estimations for the thermal conductivities of Pu, Am, Np, and Cm were made. A correlation for U-Zr alloy was also developed and extended to U-Pu-Zr and U-Pu-TRU-Zr alloys.
URI
https://scholarworks.unist.ac.kr/handle/201301/4217
URL
http://www.scopus.com/inward/record.url?partnerID=HzOxMe3b&scp=84890406112
DOI
10.1016/j.jnucmat.2013.11.018
ISSN
0022-3115
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