2009
DOI: 10.1016/j.nucengdes.2009.05.029
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Experimental investigation of turbulent flow through spacer grids in fuel rod bundles

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Cited by 40 publications
(9 citation statements)
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“…The velocity components and their fluctuations were measured in the test section at several locations varying axial elevations of 0.1-6 D H with the top edge of the spacer grid as the reference point. Caraghiaur et al (2009) presented experimental data on the pressure, velocity, and turbulence intensity in a 24 rod bundle with spacer grids. The detailed pressure measurements were carried out across the spacer grid using a specially designed sliding pressure sensing rod at a Reynolds number of 1.0 × 10 4 -5.0 × 10 4 .…”
Section: Nomenclaturementioning
confidence: 99%
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“…The velocity components and their fluctuations were measured in the test section at several locations varying axial elevations of 0.1-6 D H with the top edge of the spacer grid as the reference point. Caraghiaur et al (2009) presented experimental data on the pressure, velocity, and turbulence intensity in a 24 rod bundle with spacer grids. The detailed pressure measurements were carried out across the spacer grid using a specially designed sliding pressure sensing rod at a Reynolds number of 1.0 × 10 4 -5.0 × 10 4 .…”
Section: Nomenclaturementioning
confidence: 99%
“…The above two works, i.e., Dominguez-Ontiveros and Hassan (2009) and Caraghiaur et al (2009), were limited to an axial turbulent flow in a rod bundle with spacer grids.…”
Section: Nomenclaturementioning
confidence: 99%
“…It is essential to develop new correlations of spacer grid resistance for special designs of spacer grids and rod bundles. A sliding pressure-sensing rod in the rod bundle was employed to measure the locally axial pressure loss facing different angles in sub-channels (Caraghiaur et al, 2009). The axial pressure distribution upstream and downstream of the spacer grid facing different orienting angles is almost the same, but it is very different in the spacer grid caused by the complex geometry.…”
Section: Introductionmentioning
confidence: 99%
“…Besides that, the most works related to the numerical investigation of the coolant flow inside the channels of the complicated configuration are based on the simplified two-dimensional model of the coolant flow [9][10][11][12][13][14][15]. A numerical simulation (subchannel and CFD analysis) and an experimental investigation were applied mostly for the calculation of the thermal and hydrodynamic processes of the BWR [16][17][18][19][20]24] but not for the channel type reactor RBMK-1500.…”
Section: Introductionmentioning
confidence: 99%