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CFD analyses in tight-lattice subchannels and seven-rod bundle geometries of a Super Fast Reactor
Authors:Junli Gou  Yuki Ishiwarari  Masanori Yamakawa
Affiliation:a School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, Shaanxi 710049, PR China
b Nuclear Professional School, The University of Tokyo, Tokai-mura, Ibaraki 319-1188, Japan
c Department of Nuclear Engineering and Management, The University of Tokyo, Yayoi, Bunkyo-ku, Tokyo 113-8656, Japan
Abstract: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 °C.
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