For the heat transfer of pebble or granular beds (e.g., high temperature gas-cooled reactors (HTGR)), the particle thermal radiation is an important part. Using the subcell radiation model (SCM), which is a generic theoretical approach to predict effective thermal conductivity (ETC) of particle radiation, particle-scale investigation of the nuclear packed pebble beds filled with monosized or multicomponent pebbles is performed here. When the radial porosity distribution is considered, the ETC of the particle radiation decreases significantly at near-wall region. It is shown that radiation exchange factor increases with the surface emissivity. The results of the SCM under different surface emissivity are in good agreement with the existing correlations. The discrete heat transfer model in particle scale is presented, which combines discrete element method (DEM) and particle radiation model, and is validated by the transient experimental results. Compared with the discrete simulation results of polydisperse beds, it is found that the SCM with the effective particle diameter can be used to analyze behavior of the radiation in polydisperse beds.
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September 2018
This article was originally published in
Journal of Heat Transfer
Research-Article
Particle-Scale Investigation of Thermal Radiation in Nuclear Packed Pebble Beds
Hao Wu,
Hao Wu
Key Laboratory of Advanced Reactor
Engineering and Safety,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Ministry of Education,
Tsinghua University,
Beijing 100084, China;
Engineering and Safety,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Ministry of Education,
Tsinghua University,
Beijing 100084, China;
School of Engineering,
RMIT University,
Melbourne 3083, VIC, Australia
RMIT University,
Melbourne 3083, VIC, Australia
Search for other works by this author on:
Nan Gui,
Nan Gui
Key Laboratory of Advanced Reactor
Engineering and Safety,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Engineering and Safety,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Search for other works by this author on:
Xingtuan Yang,
Xingtuan Yang
Key Laboratory of Advanced Reactor
Engineering and Safety,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Engineering and Safety,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Search for other works by this author on:
Jiyuan Tu,
Jiyuan Tu
Key Laboratory of Advanced Reactor
Engineering and Safety,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Ministry of Education,
Tsinghua University,
Beijing 100084, China;
Engineering and Safety,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Ministry of Education,
Tsinghua University,
Beijing 100084, China;
School of Engineering,
RMIT University,
Melbourne 3083, VIC, Australia
RMIT University,
Melbourne 3083, VIC, Australia
Search for other works by this author on:
Shengyao Jiang
Shengyao Jiang
Key Laboratory of Advanced Reactor
Engineering and Safety,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Engineering and Safety,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Search for other works by this author on:
Hao Wu
Key Laboratory of Advanced Reactor
Engineering and Safety,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Ministry of Education,
Tsinghua University,
Beijing 100084, China;
Engineering and Safety,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Ministry of Education,
Tsinghua University,
Beijing 100084, China;
School of Engineering,
RMIT University,
Melbourne 3083, VIC, Australia
RMIT University,
Melbourne 3083, VIC, Australia
Nan Gui
Key Laboratory of Advanced Reactor
Engineering and Safety,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Engineering and Safety,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Xingtuan Yang
Key Laboratory of Advanced Reactor
Engineering and Safety,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Engineering and Safety,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Jiyuan Tu
Key Laboratory of Advanced Reactor
Engineering and Safety,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Ministry of Education,
Tsinghua University,
Beijing 100084, China;
Engineering and Safety,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Ministry of Education,
Tsinghua University,
Beijing 100084, China;
School of Engineering,
RMIT University,
Melbourne 3083, VIC, Australia
RMIT University,
Melbourne 3083, VIC, Australia
Shengyao Jiang
Key Laboratory of Advanced Reactor
Engineering and Safety,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
Engineering and Safety,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Ministry of Education,
Tsinghua University,
Beijing 100084, China
1Corresponding author.
Contributed by the Heat Transfer Division of ASME for publication in the JOURNAL OF HEAT TRANSFER. Manuscript received November 15, 2017; final manuscript received April 2, 2018; published online May 22, 2018. Editor: Portonovo S. Ayyaswamy.
J. Heat Transfer. Sep 2018, 140(9): 092002 (7 pages)
Published Online: May 22, 2018
Article history
Received:
November 15, 2017
Revised:
April 2, 2018
Citation
Wu, H., Gui, N., Yang, X., Tu, J., and Jiang, S. (May 22, 2018). "Particle-Scale Investigation of Thermal Radiation in Nuclear Packed Pebble Beds." ASME. J. Heat Transfer. September 2018; 140(9): 092002. https://doi.org/10.1115/1.4039913
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