The effective thermal diffusivity and conductivity of pebble bed in the high temperature gas-cooled reactor (HTGR) are two vital parameters to determine the operating temperature and power in varisized reactors with the restriction of inherent safety. A high-temperature heat transfer test facility and its inverse method for processing experimental data are presented in this work. The effective thermal diffusivity as well as conductivity of pebble bed will be measured at temperature up to 1600 °C in the under-construction facility with the full-scale in radius. The inverse method gives a global optimal relationship between thermal diffusivity and temperature through those thermocouple values in the pebble bed facility, and the conductivity is obtained by conversion from diffusivity. Furthermore, the robustness and uncertainty analyses are also set forth here to illustrate the validity of the algorithm and the corresponding experiment. A brief experimental result of preliminary low-temperature test is also presented in this work.
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July 2018
Research-Article
Method and Validation for Measurement of Effective Thermal Diffusivity and Conductivity of Pebble Bed in High Temperature Gas-Cooled Reactors
Yongyong Wu,
Yongyong Wu
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
C200, Building Nengke,
Beijing 100084, China
e-mail: wu-yy15@mails.tsinghua.edu.cn
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
C200, Building Nengke,
Beijing 100084, China
e-mail: wu-yy15@mails.tsinghua.edu.cn
Search for other works by this author on:
Cheng Ren,
Cheng Ren
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
C200, Building Nengke,
Beijing 100084, China
e-mail: rcheng@mail.tsinghua.edu.cn
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
C200, Building Nengke,
Beijing 100084, China
e-mail: rcheng@mail.tsinghua.edu.cn
Search for other works by this author on:
Rui Li,
Rui Li
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
Beijing 100084, China
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
C200, Building Nengke
,Beijing 100084, China
Search for other works by this author on:
Xingtuan Yang,
Xingtuan Yang
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
Beijing 100084, China
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
C200, Building Nengke
,Beijing 100084, China
Search for other works by this author on:
Jiyuan Tu,
Jiyuan Tu
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
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
Beijing 100084, China
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
C200, Building Nengke
,Beijing 100084, China
Search for other works by this author on:
Yongyong Wu
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
C200, Building Nengke,
Beijing 100084, China
e-mail: wu-yy15@mails.tsinghua.edu.cn
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
C200, Building Nengke,
Beijing 100084, China
e-mail: wu-yy15@mails.tsinghua.edu.cn
Cheng Ren
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
C200, Building Nengke,
Beijing 100084, China
e-mail: rcheng@mail.tsinghua.edu.cn
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
C200, Building Nengke,
Beijing 100084, China
e-mail: rcheng@mail.tsinghua.edu.cn
Rui Li
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
Beijing 100084, China
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
C200, Building Nengke
,Beijing 100084, China
Xingtuan Yang
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
Beijing 100084, China
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
C200, Building Nengke
,Beijing 100084, China
Jiyuan Tu
School of Engineering,
RMIT University,
Melbourne VIC 3083, Australia
RMIT University,
Melbourne VIC 3083, Australia
Shengyao Jiang
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
Beijing 100084, China
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
C200, Building Nengke
,Beijing 100084, China
1Corresponding author.
Manuscript received September 6, 2017; final manuscript received January 8, 2018; published online May 16, 2018. Assoc. Editor: Giacomo Grasso.
ASME J of Nuclear Rad Sci. Jul 2018, 4(3): 031006 (10 pages)
Published Online: May 16, 2018
Article history
Received:
September 6, 2017
Revised:
January 8, 2018
Citation
Wu, Y., Ren, C., Li, R., Yang, X., Tu, J., and Jiang, S. (May 16, 2018). "Method and Validation for Measurement of Effective Thermal Diffusivity and Conductivity of Pebble Bed in High Temperature Gas-Cooled Reactors." ASME. ASME J of Nuclear Rad Sci. July 2018; 4(3): 031006. https://doi.org/10.1115/1.4039035
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