Microstructure-Based Thermal Conductivity and Thermal Behavior Modeling of Nuclear Fuel UO2-BeO-Reference-Cited by-同舟云学术

Microstructure-Based Thermal Conductivity and Thermal Behavior Modeling of Nuclear Fuel UO2-BeO

Published:2017-07-13 Issue:9 Volume:39 Page:760-774
ISSN:0145-7632
Container-title:Heat Transfer Engineering
language:en
Short-container-title:Heat Transfer Engineering

Author:

Zhou Wenzhong¹²,Revankar Shripad T.³⁴,Liu Rong¹,Beni Mehrdad Shahmohammadi¹

Affiliation:

1. Department of Mechanical and Biomedical Engineering, City University of Hong Kong, Hong Kong, China

2. Center for Advanced Nuclear Safety and Sustainable Development, City University of Hong Kong, Hong Kong, China

3. School of Nuclear Engineering, Purdue University, West Lafayette, Indiana, USA

4. Division of Advanced Nuclear Engineering, Pohang University of Science and Technology, Pohang, Gyeongbuk, Korea

Publisher

Informa UK Limited

Subject

Fluid Flow and Transfer Processes,Mechanical Engineering,Condensed Matter Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/01457632.2017.1341216

Reference42 articles.

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2. Frost, B. R. T. Nuclear Fuel Elements: Design, Fabrication, Performance, Pergamon Press, NY. pp. 35–36, 50–70, 72, 177–190, 232, 1982.

3. Holden, R.B. Ceramic Fuel Elements, Gordon and Breach Science Publishers, NY. pp. 59–75, 213–217, 1966.

4. Belle, J. Uranium Dioxide: Properties and Nuclear Applications, US AEC Report, Germantown, Maryland, pp. 477–545, 1961.

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