| NUCLEAR AND NEW ENERGY ENGINEERING |
|
|
|
|
|
Modeling of the heat transfer characteristics of the effective thermal conductivity test facility for high temperature gas-cooled reactors |
| REN Cheng1, YANG Xingtuan1, LI Congxin2, SUN Yanfei1, LIU Zhiyong1 |
1. Key Laboratory of Advanced Reactor Engineering and Safety of the Ministry of Education, Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China;
2. Nuclear and Radiation Safety Center, Ministry of Environmental Protection of the People's Republic of China, Beijing 100088, China |
|
|
|
|
Abstract The effective thermal conductivity is a characteristic parameter which represents the macroscopic heat transfer ability of the pebble bed type core of the high temperature gas-cooled reactor. A full-scale effective thermal conductivity measurement facility was developed by the Institute of Nuclear and New Energy Technology of Tsinghua University to improve calculations and safety analyses of the Chinese high temperature gas-cooled reactor design using experiments in a static graphite pebble bed in a vacuum or helium environment. A simplified two-dimensional model was used to simulate the thermal conduction and radiation characteristics of the facility under vacuum and at high temperatures. The steady and transient heat transfer characteristics were calculated to assess the radial temperature distribution in the pebble bed zone, the influences of different materials in the top and bottom insulating layers, overheating of the central heaters and temperature increases and decreases to guide operation of the experimental facility.
|
| Keywords
high temperature gas-cooled reactor
effective thermal conductivity
high temperature and vacuum condition
temperature distribution calculation
|
|
|
|
Issue Date: 15 September 2015
|
|
|
[1] ZHANG Zuoyi, YU Suyuan. Future HTGR developments in China after the criticality of the HTR-10 [J]. Nuclear Engineering and Design, 2002, 218(1): 249-257
[2] ZHANG Zuoyi, WU Zongxin, WANG Dazhong, et al. Current status and technical description of Chinese 2×250 MWth HTR-PM demonstration plant [J]. Nuclear Engineering and Design, 2009, 239(7): 1212-1219.
[3] TANG Chunhe, TANG Yaping, ZHU Junguo, et al. Design and manufacture of fuel element for the 10 MW high temperature gas-cooled reactor [J]. Nuclear Engineering and Design, 2002, 218(1): 91-102.
[4] ZHANG Zuoyi, WU Zongxin, SUN Yuliang, et al. Design aspects of the Chinese modular high-temperature gas-cooled reactor HTR-PM [J]. Nuclear Engineering and Design, 2006, 236(5): 485-490.
[5] REN Cheng, YANG Xingtuan, SUN Yanfei. Porous structure analysis of the packed beds in a high-temperature reactor pebble bed modules heat transfer test facility [J]. Chinese Physics Letters. 2013, 30 (2): 022801
[6] REN Cheng, YANG Xingtuan, LI Congxin, et al. Design of the material performance test apparatus for high temperature gas-cooled reactor [J]. Nuclear Science and Techniques, 2013, 24(6): 060602(1-5)
[7] Donne M D, Sordon G. Heat transfer in pebble beds for fusion blankets [J]. Fusion Technol. 1990, 17(4): 597-635.
[8] Aquaro D, Zaccari N. Pebble bed thermal mechanical theoretical model: Application at the geometry of test blanket module of ITER-FEAT nuclear fusion reactor [J]. Fusion Engineering and Design, 2005, 75: 903-909
[9] Rousseau P G, van Staden M. Introduction to the PBMR heat transfer test facility [J]. Nuclear Engineering and Design, 2008, 238(11): 3060-3072.
[10] Van Antwerpen W, Du Toit C G, Rousseau P G. A review of correlations to model the packing structure and effective thermal conductivity in packed beds of mono-sized spherical particles [J]. Nuclear Engineering and Design, 2010, 240(7): 1803-1818.
[11] Rousseau P G, Du Toit C G, Landman W A. Validation of a transient thermal-fluid systems CFD model for a packed bed high temperature gas-cooled nuclear reactor [J]. Nuclear Engineering and Design, 2006, 236(5): 555-564.
[12] Nieβen A F, Stocker B. Sana-1 code-to-experiment summary description of benchmark [C]// Proceedings of the 3rd IAEA Research Coordination Meeting on Heat Transport and Afterheat Removal for Gas-Cooled Reactors under Accident Conditions. Vienna, Austria: International Atomic Energy Agency, 1995.
[13] Achenbach E. Heat and flow characteristics of packed beds [J]. Experimental Thermal and Fluid Sciences. 1995, 10(1): 17-27
[14] Bauer R, Schliinder E U, Effective radial thermal conductivity of packings in gas flow [J]. International Journal of Chemical Engineering 1978, 18(2): 181-204. |
|
Viewed |
|
|
|
Full text
|
|
|
|
|
Abstract
|
|
|
|
|
Cited |
|
|
|
|
| |
Shared |
|
|
|
|
| |
Discussed |
|
|
|
|
2015,
Vol. 55
