CFD analyses in tight-lattice subchannels and seven-rod bundle geometries of a Super Fast Reactor

被引:7
|
作者
Gou, Junli [1 ,2 ]
Ishiwarari, Yuki [3 ]
Oka, Yoshiaki [2 ,3 ]
Yamakawa, Masanori [2 ]
机构
[1] Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Xian 710049, Shaanxi, Peoples R China
[2] Univ Tokyo, Nucl Profess Sch, Tokai, Ibaraki 3191188, Japan
[3] Univ Tokyo, Dept Nucl Engn & Management, Bunkyo Ku, Tokyo 1138656, Japan
关键词
SUPERCRITICAL WATER; HEAT-TRANSFER; FUEL;
D O I
10.1016/j.nucengdes.2011.02.013
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
This paper presents CFD analyses in heat unsymmetric subchannels and heat symmetric seven-rod bundle geometries of a Super Fast Reactor (Super FR) fuel assembly using STAR-CD. The purpose of CFD analyses in heat unsymmetric subchannels is to evaluate the effect of the power differences on the heat transfer in subchannels of the Super Fast Reactor. For heat symmetric seven-rod bundles, the effects of the gap clearance between the fuel rod and the assembly wall and the displacement of the fuel rod on the circumferential temperature distributions and Maximum Cladding Surface Temperature (MCST) are analyzed. The results show that larger power difference between fuel rods gives larger circumferential temperature difference of the hottest fuel rods. Considering cross flow between edge and ordinary subchannels, 1 mm gap between the fuel rod and the assembly wall is better for small MCST although the circumferential temperature difference in edge subchannel is large. MCST increases exponentially with the displacement. The relative error of displacement should be less than 1% if the allowable increment of MCST due to displacement is less than 6 degrees C. (C) 2011 Elsevier B.V. All rights reserved.
引用
收藏
页码:1656 / 1666
页数:11
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