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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2015.1
- 수록면
- 523 - 533 (11page)
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초록· 키워드
오류제보하기
Three-dimensional flow phenomena in a wire-wrapped 37-pin fuel assembly mock-up of aJapanese loop-type sodium-cooled fast reactor, Monju, were investigated with a numericalanalysis using a general-purpose commercial computational fluid dynamics code, CFX.
Complicated and vortical flow phenomena in the wire-wrapped 37-pin fuel assembly werecaptured by a Reynolds-averaged NaviereStokes flow simulation using a shear stresstransport turbulence model. The main purpose of the current study is to understand thethree-dimensional complex flow phenomena in a wire-wrapped fuel assembly to supportthe license issue for the core design. Computational fluid dynamics results show goodagreement with friction factor correlation models. The secondary flow in the corner andedge subchannels is much stronger than that in an interior subchannel. The axial velocityaveraged in the corner and edge subchannels is higher than that averaged in the interiorsubchannels. Three-dimensional multiscale vortex structures start to be formed by aninteraction between secondary flows around each wire-wrapped pin. Behavior of the largescalevortex structures in the corner and edge subchannels is closely related to the relativeposition between the hexagonal duct wall and the helically wrapped wire spacer. Thesmall-scale vortex is axially developed in the interior subchannels. Furthermore, a drivingforce on each wire spacer surface is closely related to the relative position between thehexagonal duct wall and the wire spacer.
목차
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참고문헌 (23)
참고문헌 신청
E.H. Novendstern / 1972 / Turbulent flow pressure drop model for fuel rod assemblies utilizing a helical wire-wrap spacer system / Nucl. Eng. Des 22:19~27
K. Rehme / 1973 / Pressure drop correlations for fuel element spacers / Nucl. Technol 17:15~23
F.C. Engel / 1979 / Laminar, transition and turbulent parallel flow pressure drop across wire-wrapspaced rod bundles / Nucl. Sci. Eng 69:290~296
S.K. Cheng / 1986 / Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundlesdbundle friction factors, sub-channel friction factors and mixing parameters / Nucl. Eng. Des 92:227~251
R.M. Roidt / Experimental determination of interior subchannel crossflow and axial flow in a model of the Clinch River Breeder Reactor fuel assembly rod bundle with wire wrap spacers
K. Rehme / 1973 / Pressure drop correlations for fuel element spacers / Nucl. Technol 17:15~23
F.C. Engel / 1979 / Laminar, transition and turbulent parallel flow pressure drop across wire-wrapspaced rod bundles / Nucl. Sci. Eng 69:290~296
S.K. Cheng / 1986 / Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundlesdbundle friction factors, sub-channel friction factors and mixing parameters / Nucl. Eng. Des 92:227~251
R.M. Roidt / Experimental determination of interior subchannel crossflow and axial flow in a model of the Clinch River Breeder Reactor fuel assembly rod bundle with wire wrap spacers
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