Title :
Numerical simulation of hydraulic characteristics of coolant in rod spacer grids
Author :
Teng-da, Ma ; Zeng He-yi ; Guo Yun
Author_Institution :
Coll. of Nucl. Sci. & Technol., Harbin Eng. Univ., Harbin, China
Abstract :
Thermal hydraulic performance analysis of fuel rod bundle with spacer grids takes important role among the pressure water reactor (PWR) design and safety operation. Due to its intrinsic complex geometric configuration, previous studies were almost based on one-dimensional code and many simplifications had to be made to make simulations manageable. In the present paper, the intact and simplified spacer grids were simulated and analyzed by using the Computational Fluid Dynamic (CFD) software, and efforts were emphasized on the influence factors on the flow field including spacer grids with mixing vanes only and spacer grids with mixing vanes springs and dimples, respectively. The results indicate that the springs and dimples have great influences on the flow field and thus cannot be neglected during numerical simulation of coolant flow through subchannels with spacer grids. The transverse flows and pressure drop with springs and dimples show more intense than those without spacer and dimples as expected.
Keywords :
computational fluid dynamics; fission reactor coolants; fission reactor cooling; fission reactor design; fission reactor safety; numerical analysis; power grids; computational fluid dynamic software; coolant; fuel rod; numerical simulation; pressure water reactor design; spacer grids; thermal hydraulic performance analysis; Computational fluid dynamics; Finite element methods; Frequency locked loops; CFD; Fuel rod bundle; Reactor; Spacer grids; Thermal hydraulics;
Conference_Titel :
Information Systems for Crisis Response and Management (ISCRAM), 2011 International Conference on
Conference_Location :
Harbin, Heilongjiang
Print_ISBN :
978-1-4577-0369-0
DOI :
10.1109/ISCRAM.2011.6184062