| MECHANICAL ENGINEERING |
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Dynamics characteristics of collisions between fuel elements transported in tandem in a pebble-bed reactor system |
| LIU Hongbing, HUANG An, CHANG Baohua, WANG Li, DU Dong |
| Key Laboratory for Advanced Materials Processing Technology, Department of Mechanical Engineering, Tsinghua University, Beijing 100084, China |
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Abstract Spherical fuel elements are lifted pneumatically into an array of tubes outside the core in a pebble-bed reactor with the flow in the tubes perpendicular to the flow in the core. Sometimes two fuel elements are very close in the pipeline so they are transported in tandem, which increases the fuel element transportation efficiency. When lifted, the fuel elements may collide with each other with the characteristics of these collisions providing an important basis for evaluating the reliability of the transport system. This study analyzed the flow characteristics in the pipeline using computational fluid dynamics to determine the forces on the fuel elements. A dynamic model of the fuel elements was then developed to describe the impact characteristics. The results demonstrate that the collision force will not damage the fuel elements and that the fuel elements will be lifted together after several collisions. The lifting process is steady and the lifting is efficient. Experimental tests validate the accuracy of the theoretical analysis. This research provides a basis for designing pneumatic transport systems for fuel elements in pebble-bed reactors.
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| Keywords
reactor fluid mechanics
pebble-bed reactor
dynamics
pneumatic transportation
fuel element
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Issue Date: 15 September 2016
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[1] Zhang Z, Wu Z, Wang D, 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.
[2] Liu J, Xiao H, Li C. Design and full scale test of the fuel handling system [J]. Nuclear Engineering and Design, 2002, 218(1-3): 169-178.
[3] 经荥清, 杨永伟, 古玉祥, 等. HTR-10初次临界装料预估 [J]. 清华大学学报(自然科学版), 2001, 41(4/5): 116-119.JING Xingqing, YANG Yongwei, GU Yuxiang, et al. Prediction calculation of HTR-10 fuel loading for the first criticality [J]. J Tsinghua Univ (Sci & Tech), 2001, 41(4/5): 116-119. (in Chinese)
[4] 沈鹏, 刘洪冰, 都东, 等. 球床反应堆燃料元件成组串列管路气力提升方法研究 [J]. 高技术通讯, 2013, 23(5): 519-524. SHEN Peng, LIU Hongbing, DU Dong, et al. Research on a method for grouped tandem pneumatic lifting a pebble-bed reactor's fuel element transportation in pipelines [J]. High Technology Letters, 2013, 23(5): 519-524. (in Chinese)
[5] 刘继国, 肖宏伶, 王伟成. 10 MW高温气冷实验堆燃料元件装卸系统研制 [J]. 原子能科学技术, 2003, 37(4): 334-339.LIU Jiguo, XIAO Hongling, WANG Weicheng. Development of the fuel handling system in 10 MW high temperature gas-cooled reactor [J]. Atomic Energy Science and Technology, 2003, 37(4): 334-339. (in Chinese)
[6] 胡坤, 李振北. ANSYS ICEM CFD工程实例详解 [M]. 北京: 人民邮电出版社, 2014.HU Kun, LI Zhenbei. Detailed Introduction of Engineering Case of ANSYS ICEM CFD [M]. Beijing: Post & Telecom Press, 2014. (in Chinese)
[7] 王丰. 液体和气体的热物理性质表 [M]. 北京: 科学出版社, 1982.WANG Feng. Thermophysical Properties of Liquids and Gases [M]. Beijing: Science Press, 1982. (in Chinese)
[8] Tang C, Tang Y, Zhu J, et al. Research and development of fuel element for Chinese 10 MW high temperature gas-cooled reactor [J]. Journal of Nuclear Science and Technology, 2000, 37(9): 802-806.
[9] 陈志鹏, 雒晓卫, 于溯源. 输送速度对高温气冷堆燃料装卸系统提升段石墨球磨损性能的影响 [J]. 原子能科学技术, 2012, 46(Suppl): 853-858.CHEN Zhipeng, LUO Xiaowei, YU Suyuan. Effect of feeding velocity on wear behavior of graphite ball under elevating process with HTGR fuel handling system [J]. Atomic Energy Science and Technology, 2012, 46(Suppl): 853-858. (in Chinese)
[10] 阎超. 计算流体力学方法及应用 [M]. 北京: 北京航空航天大学出版社, 2006.YAN Chao. Method and Application of Computational Fluid Dynamics [M]. Beijing: Beihang University Press, 2006. (in Chinese)
[11] Liu H, Du D, Han Z, et al. Dynamic analysis and application of fuel elements pneumatic transportation in a pebble bed reactor [J]. Energy, 2015, 79: 33-39.
[12] Ikushima T, Honma T, Ishizuka H. Seismic research on block-Type HTGR core [J]. Nuclear Engineering and Design, 1982, 71(2): 195-215.
[13] 卢振明, 张杰, 周湘文, 等. HTGR燃料元件炭化工艺优化 [J]. 核动力工程, 2013, 34(5): 71-75.LU Zhenming, ZHANG Jie, ZHOU Xiangwen, et al. Optimization of carbonization process in manufacture of fuel elements for HTGR [J]. Nuclear Power Engineering, 2013, 34(5): 71-75. (in Chinese)
[14] 唐春和. HTR-10燃料元件的制造和发展趋势 [J]. 核标准计量与质量, 2006(3): 2-12.TANG Chunhe. Manufacture and development trend of fuel element in HTR-10 [J]. He Biaozhun Jiliang Yu Zhiliang, 2006(03): 2-12. (in Chinese) |
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2016,
Vol. 56
