In nuclear packed pebble beds, it is a fundamental task to model effective thermal conductivity (ETC) of thermal radiation. Based on the effective heat transfer cells of structured packing, a short-range radiation model (SRM) and a subcell radiation model (SCM) are applied to obtain analytical results of ETC. It is shown that the SRM of present effective heat transfer cells are in good agreement with the numerical simulations of random packing and it is only slightly higher than empirical correlations when temperature exceeds 1200 °C. In order to develop a generic theoretical approach of modeling ETC, the subcell radiation model is presented and in good agreement with Kunii–Smith correlation, especially at very high temperature ranges (over 1500 °C). Based on SCM, one-dimensional (1D) radial heat transfer model is applied in the analysis of the HTTU experiments. The results of ETC and radial temperature distribution are in good agreement with the experimental data.
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Modeling Effective Thermal Conductivity of Thermal Radiation for Nuclear Packed Pebble Beds
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;
School of Engineering,
RMIT University,
Melbourne, VIC 3083, Australia
RMIT University,
Melbourne, VIC 3083, Australia
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, VIC 3083, Australia
RMIT University,
Melbourne, VIC 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;
School of Engineering,
RMIT University,
Melbourne, VIC 3083, Australia
RMIT University,
Melbourne, VIC 3083, Australia
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, VIC 3083, Australia
RMIT University,
Melbourne, VIC 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
1Corresponding author.
Contributed by the Heat Transfer Division of ASME for publication in the JOURNAL OF HEAT TRANSFER. Manuscript received April 3, 2017; final manuscript received August 22, 2017; published online December 27, 2017. Assoc. Editor: Laurent Pilon.
J. Heat Transfer. Apr 2018, 140(4): 042701 (6 pages)
Published Online: December 27, 2017
Article history
Received:
April 3, 2017
Revised:
August 22, 2017
Citation
Wu, H., Gui, N., Yang, X., Tu, J., and Jiang, S. (December 27, 2017). "Modeling Effective Thermal Conductivity of Thermal Radiation for Nuclear Packed Pebble Beds." ASME. J. Heat Transfer. April 2018; 140(4): 042701. https://doi.org/10.1115/1.4038231
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