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http://dx.doi.org/10.3795/KSME-A.2012.36.12.1653

Pressure Drop Variations and Structural Characteristics of SMART Nuclear Fuel Assembly Caused by Coolant Flow  

Jin, Hai Lan (Dept. of Mechanical Engineering, Chungnam Nat'l Univ.)
Lee, Young Shin (Dept. of Mechanical Engineering, Chungnam Nat'l Univ.)
Lee, Hyun Seung (Dept. of Mechanical Engineering, Chungnam Nat'l Univ.)
Park, Nam Gyu (R&D Center, KEPCO Nuclear Fuel)
Publication Information
Transactions of the Korean Society of Mechanical Engineers A / v.36, no.12, 2012 , pp. 1653-1661 More about this Journal
Abstract
In this study, the pressure drop changes and structural characteristics of a SMART rod bundle under the effect of a coolant were investigated. The turbulence model of the BSL Reynolds stress model was used to model the coolant flow, and a fluid solid interaction simulation was conducted. First, fuel rod vibration analysis was performed to confirm the natural frequency of the fuel rod, which was supported by spacer grid assemblies, and this was compared with experimental results. From the experimental results, the natural frequency was found to be 48 Hz, and the error compared with the simulation results was 2%. The pressure drop at the rod bundle was calculated and compared with the experimental data; it showed an error of 8%, demonstrating the simulation accuracy. In the flow analysis, the flow velocity and secondary flow at different domains were calculated, and vortex generation was also observed. Finally, through the fluid solid interaction analysis, the fuel rod displacements caused by flow-induced vibrations were calculated. Then, calculated displacement PSD at maximum displacement happed point.
Keywords
Fuel Rod; Nuclear Fuel Assembly; Spacer Grid Assembly; Pressure Drop; Structure Characteristics;
Citations & Related Records
Times Cited By KSCI : 3  (Citation Analysis)
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