Investigation of Wall Effect on Packing Structures and Purge Gas Flow Characteristics in Pebble Beds for Fusion Blanket by Combining Discrete Element Method and Computational Fluid Dynamics Simulation

被引:1
|
作者
Gong, Baoping [1 ]
Cheng, Hao [1 ]
Zhou, Bing [1 ]
Yan, Juemin [1 ]
Wang, Long [1 ]
Zhang, Long [1 ]
Feng, Yongjin [2 ]
Wang, Xiaoyu [1 ]
机构
[1] Southwestern Inst Phys, Chengdu 610041, Peoples R China
[2] Nucl Power Inst China, Chengdu 610041, Peoples R China
来源
APPLIED SCIENCES-BASEL | 2024年 / 14卷 / 06期
关键词
pebble bed; flow characteristic; helium gas; pressure drops; DEM-CFD; HELIUM PRESSURE-DROP; RANDOMLY PACKED-BED; DEM-CFD SIMULATION; SIZED PEBBLES; VALIDATION; MODEL;
D O I
10.3390/app14062289
中图分类号
O6 [化学];
学科分类号
0703 ;
摘要
In a tritium-breeding blanket of a fusion reaction, helium, used as a tritium-purging gas, will purge the tritium breeder pebble beds to extract the tritium in blanket. The purge gas flow characteristics will affect the tritium extraction efficiency. The effect of the fixed wall on the pebble packing structures and purge gas flow characteristics was investigated by combining the discrete element method (DEM) and computational fluid dynamics (CFD) method. The results indicate that the fixed wall leads to a regular packing of the pebbles adjacent to the fixed wall in association with drastic fluctuations in the porosity of the pebble bed, which can affect the purge gas flow behaviors. Further analyses of helium flow behaviors show that the helium pressure in the pebble bed decreases in a linear manner along the flow direction, whereas the pressure drop gradient of helium increases gradually with an increase in the packing factor. The reduction in porosity in the pebble bed leads to a notable escalation in helium flow velocity. Concerning the direction perpendicular to the helium gas flow, the evolution of the cut-plane averaged velocity of helium is similar to that of the porosity, except in the region immediately adjacent to the wall. The pressure drop and flow characteristics obtained in this study can serve as input for the thermohydraulic analysis of the tritium blowing systems in the tritium-breeding blanket of a fusion reactor.
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页数:19
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