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.
任成, 杨星团, 李聪新, 孙艳飞, 刘志勇. 高温气冷堆球床等效导热系数实验装置模拟计算[J]. 清华大学学报（自然科学版）, 2015, 55(9): 991-997.
REN Cheng, YANG Xingtuan, LI Congxin, SUN Yanfei, LIU Zhiyong. Modeling of the heat transfer characteristics of the effective thermal conductivity test facility for high temperature gas-cooled reactors. Journal of Tsinghua University(Science and Technology), 2015, 55(9): 991-997.
 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
 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.
 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.
 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.
 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
 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)
 Donne M D, Sordon G. Heat transfer in pebble beds for fusion blankets [J]. Fusion Technol. 1990, 17(4): 597-635.
 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
 Rousseau P G, van Staden M. Introduction to the PBMR heat transfer test facility [J]. Nuclear Engineering and Design, 2008, 238(11): 3060-3072.
 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.
 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.
 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.
 Achenbach E. Heat and flow characteristics of packed beds [J]. Experimental Thermal and Fluid Sciences. 1995, 10(1): 17-27
 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.