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Title: Heat transfer simulations of the UO2 particle–graphite system in TREAT fuel

Authors:
ORCiD logo; ; ;
Publication Date:
Sponsoring Org.:
USDOE
OSTI Identifier:
1254665
Resource Type:
Publisher's Accepted Manuscript
Journal Name:
Nuclear Engineering and Design
Additional Journal Information:
Journal Name: Nuclear Engineering and Design Journal Volume: 293 Journal Issue: C; Journal ID: ISSN 0029-5493
Publisher:
Elsevier
Country of Publication:
Netherlands
Language:
English

Citation Formats

Mo, Kun, Yun, Di, Yacout, Abdellatif M., and Wright, Arthur E. Heat transfer simulations of the UO2 particle–graphite system in TREAT fuel. Netherlands: N. p., 2015. Web. doi:10.1016/j.nucengdes.2015.08.009.
Mo, Kun, Yun, Di, Yacout, Abdellatif M., & Wright, Arthur E. Heat transfer simulations of the UO2 particle–graphite system in TREAT fuel. Netherlands. https://doi.org/10.1016/j.nucengdes.2015.08.009
Mo, Kun, Yun, Di, Yacout, Abdellatif M., and Wright, Arthur E. Sun . "Heat transfer simulations of the UO2 particle–graphite system in TREAT fuel". Netherlands. https://doi.org/10.1016/j.nucengdes.2015.08.009.
@article{osti_1254665,
title = {Heat transfer simulations of the UO2 particle–graphite system in TREAT fuel},
author = {Mo, Kun and Yun, Di and Yacout, Abdellatif M. and Wright, Arthur E.},
abstractNote = {},
doi = {10.1016/j.nucengdes.2015.08.009},
journal = {Nuclear Engineering and Design},
number = C,
volume = 293,
place = {Netherlands},
year = {Sun Nov 01 00:00:00 EDT 2015},
month = {Sun Nov 01 00:00:00 EDT 2015}
}

Journal Article:
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Cited by: 6 works
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