Radiative and conductive heat transfer is fairly important in the nuclear pebble bed. A continuum model is proposed here to derive the effective thermal conductivity (ETC) of pebble bed. It is a physics-based equation determined by the temperature, number density, heat transfer coefficient, and the radial distribution function (RDF). Based on a concept of continuum, this model considers the conduction and thermal radiation in nuclear pebble bed through a uniform framework and the results are in good agreement with the existing model and correlations. It indicates that the local temperature in the radiation case without internal heat sources is determined by all possible surrounding pebbles weighted by a radiative kernel function. The discrete element method (DEM) packing results are in good agreement with the solution of the continuum model. Both the conductive and radiative continuum models converge to the heat conduction in continuum mechanics at size factor μ ≪ 1.
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A New Uniform Continuum Modeling of Conductive and Radiative Heat Transfer in Nuclear Pebble Bed
Hao Wu,
Hao Wu
Institute of Nuclear and New Energy Technology,
Collaborative Innovation Center of Advanced
Nuclear Energy Technology,
Key Laboratory of Advanced Reactor
Engineering and Safety,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Collaborative Innovation Center of Advanced
Nuclear Energy Technology,
Key Laboratory of Advanced Reactor
Engineering and Safety,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Search for other works by this author on:
Nan Gui,
Nan Gui
Institute of Nuclear and New Energy Technology,
Collaborative Innovation Center of Advanced
Nuclear Energy Technology,
Key Laboratory of Advanced Reactor
Engineering and Safety,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Collaborative Innovation Center of Advanced
Nuclear Energy Technology,
Key Laboratory of Advanced Reactor
Engineering and Safety,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Search for other works by this author on:
Xingtuan Yang,
Xingtuan Yang
Institute of Nuclear and New Energy Technology,
Collaborative Innovation Center of Advanced
Nuclear Energy Technology,
Key Laboratory of Advanced Reactor
Engineering and Safety,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Collaborative Innovation Center of Advanced
Nuclear Energy Technology,
Key Laboratory of Advanced Reactor
Engineering and Safety,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Search for other works by this author on:
Jiyuan Tu,
Jiyuan Tu
Institute of Nuclear and New Energy Technology,
Collaborative Innovation Center of Advanced
Nuclear Energy Technology,
Key Laboratory of Advanced Reactor
Engineering and Safety,
Ministry of Education,
Tsinghua University,
Beijing 100084, China;
Collaborative Innovation Center of Advanced
Nuclear Energy Technology,
Key Laboratory of Advanced Reactor
Engineering and Safety,
Ministry of Education,
Tsinghua University,
Beijing 100084, China;
School of Engineering,
RMIT University,
Melbourne, Victoria 3083, Australia
RMIT University,
Melbourne, Victoria 3083, Australia
Search for other works by this author on:
Shengyao Jiang
Shengyao Jiang
Institute of Nuclear and New Energy Technology,
Collaborative Innovation Center of Advanced
Nuclear Energy Technology,
Key Laboratory of Advanced Reactor
Engineering and Safety,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Collaborative Innovation Center of Advanced
Nuclear Energy Technology,
Key Laboratory of Advanced Reactor
Engineering and Safety,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Search for other works by this author on:
Hao Wu
Institute of Nuclear and New Energy Technology,
Collaborative Innovation Center of Advanced
Nuclear Energy Technology,
Key Laboratory of Advanced Reactor
Engineering and Safety,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Collaborative Innovation Center of Advanced
Nuclear Energy Technology,
Key Laboratory of Advanced Reactor
Engineering and Safety,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Nan Gui
Institute of Nuclear and New Energy Technology,
Collaborative Innovation Center of Advanced
Nuclear Energy Technology,
Key Laboratory of Advanced Reactor
Engineering and Safety,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Collaborative Innovation Center of Advanced
Nuclear Energy Technology,
Key Laboratory of Advanced Reactor
Engineering and Safety,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Xingtuan Yang
Institute of Nuclear and New Energy Technology,
Collaborative Innovation Center of Advanced
Nuclear Energy Technology,
Key Laboratory of Advanced Reactor
Engineering and Safety,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Collaborative Innovation Center of Advanced
Nuclear Energy Technology,
Key Laboratory of Advanced Reactor
Engineering and Safety,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Jiyuan Tu
Institute of Nuclear and New Energy Technology,
Collaborative Innovation Center of Advanced
Nuclear Energy Technology,
Key Laboratory of Advanced Reactor
Engineering and Safety,
Ministry of Education,
Tsinghua University,
Beijing 100084, China;
Collaborative Innovation Center of Advanced
Nuclear Energy Technology,
Key Laboratory of Advanced Reactor
Engineering and Safety,
Ministry of Education,
Tsinghua University,
Beijing 100084, China;
School of Engineering,
RMIT University,
Melbourne, Victoria 3083, Australia
RMIT University,
Melbourne, Victoria 3083, Australia
Shengyao Jiang
Institute of Nuclear and New Energy Technology,
Collaborative Innovation Center of Advanced
Nuclear Energy Technology,
Key Laboratory of Advanced Reactor
Engineering and Safety,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Collaborative Innovation Center of Advanced
Nuclear Energy Technology,
Key Laboratory of Advanced Reactor
Engineering and Safety,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Contributed by the Heat Transfer Division of ASME for publication in the JOURNAL OF HEAT TRANSFER. Manuscript received February 1, 2019; final manuscript received May 7, 2019; published online June 17, 2019. Editor: Portonovo S. Ayyaswamy.
J. Heat Transfer. Aug 2019, 141(8): 082001 (5 pages)
Published Online: June 17, 2019
Article history
Received:
February 1, 2019
Revised:
May 7, 2019
Citation
Wu, H., Gui, N., Yang, X., Tu, J., and Jiang, S. (June 17, 2019). "A New Uniform Continuum Modeling of Conductive and Radiative Heat Transfer in Nuclear Pebble Bed." ASME. J. Heat Transfer. August 2019; 141(8): 082001. https://doi.org/10.1115/1.4043852
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