کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
297893 511769 2011 11 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
CFD analyses in tight-lattice subchannels and seven-rod bundle geometries of a Super Fast Reactor
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
CFD analyses in tight-lattice subchannels and seven-rod bundle geometries of a Super Fast Reactor
چکیده انگلیسی

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.


► We do CFD analyses in subchannels and seven-rod bundle geometries of a Super FR. Larger power difference between rods gives larger peripheral temperature gradient.
► 1 mm gap between the fuel rod and the assembly wall is better for small MCST.
► MCST increases exponentially with the displacement.
► The relative displacement error should be less than 1% with a MCST increment of 6 °C.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Engineering and Design - Volume 241, Issue 5, May 2011, Pages 1656–1666
نویسندگان
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