• Title/Summary/Keyword: Rod bundle

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Turbulent Flow in an Axially Finned Rod Bundle with Spacer Grids

  • Chung, H.J.;Cho, S.;Chun, S.Y.;Yang, S.K.;Chung, M.K.
    • Nuclear Engineering and Technology
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    • v.30 no.4
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    • pp.328-341
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    • 1998
  • This paper presents in detail the hydraulic characteristic measurements using LDV(Laser Doppler Velocimetry) in subchannels of a HANARO, KAERI research reactor, fuel bundle. The fuel bundle consists of 18 axially finned rods with 3 spacer grids and has a cylindrical configuration. Axial velocity and turbulent intensity were measured. The effects of the spacer grids on the turbulent flow were investigated using the experimental results. Pressure drops for each component of the fuel bundle were measured, and the friction factors of the fuel bundle and the loss coefficients for the spacer grids were estimated from the measured pressure drops. The turbulent thermal mixing phenomena were discussed.

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Pressure Drop Variations and Structural Characteristics of SMART Nuclear Fuel Assembly Caused by Coolant Flow (냉각유동에 의한 SMART 핵연료집합체의 압력강하변화 및 구조특성)

  • Jin, Hai Lan;Lee, Young Shin;Lee, Hyun Seung;Park, Nam Gyu
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.36 no.12
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    • pp.1653-1661
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    • 2012
  • 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.

The Optical Design of Miniaturized Microscope Objective for CARS Imaging Catheter with Fiber Bundle

  • Rim, Cheon-Seog
    • Journal of the Optical Society of Korea
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    • v.14 no.4
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    • pp.424-430
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    • 2010
  • In coherent anti-Stokes Raman scattering (CARS) microscopy reported until now, conventional microscope objectives are used, so that they are limited for introduction into a living body. Gradient-index (GRIN) rod lenses might be a solution for miniaturized microscope objectives for in-vivo CARS microscopy. However, due to the inherent large amount of chromatic aberration, GRIN rod lenses cannot be utilized for this purpose. CARS imaging catheter, composed of miniaturized microscope objective and fiber bundle, can be introduced into a living body for minimally invasive diagnosis. In order to design the catheter, we have to first investigate design requirements. And then, the optical design is processed with design strategies and intensive computing power to achieve the design requirements. We report the miniaturized objective lens system with diffraction-limited performance and completely corrected chromatic aberrations for an in-vivo CARS imaging catheter.

Effect of Spacer Grids on CHF at PWR Operating Conditions

  • Ahn, Seung-Hoon;Jeun, Gyoo-Dong
    • Nuclear Engineering and Technology
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    • v.33 no.3
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    • pp.283-297
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    • 2001
  • The CHF in PWR rod bundles is usually predicted by the local flow correlation approach based on subchannel analysis while difficulty exists due to the existence of spacer grids especially with mixing vanes. In order to evaluate the effect of spacer grids on CHF, the experimental rod bundle data with various types of spacer grids were analyzed using the subchannel code, COBRA-IV-i. For the Plain grid data, a CHF correlation was described as a function of local flow conditions and heated length, and then the residuals of the CHF in mixing vaned grids predicted by the correlation were examined in various kinds of grids. In order to compensate for the residual, three parameters, distances between grids and from the last grids to the CHF site, and equivalent hydraulic diameter were introduced into a grid parameter function representing the remaining effect of spacer grids predicted most of the CHF data points in plaing grids within $\pm$20 percent error band. Good agreement with the CHF data was also shown when the grid parameter function for mixing vaned grids of a specific design was used to compensate for the residuals of the CHF data predicted by the correlation.

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