Experimental determination and analysis of the transverse pressure difference in a wire-wrapped rod bundle
Published 2021 View Full Article
- Home
- Publications
- Publication Search
- Publication Details
Title
Experimental determination and analysis of the transverse pressure difference in a wire-wrapped rod bundle
Authors
Keywords
Transverse pressure difference, Wire-wrapped rod bundles, Reynolds number, Hexagonal duct
Journal
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER
Volume 170, Issue -, Pages 120958
Publisher
Elsevier BV
Online
2021-02-04
DOI
10.1016/j.ijheatmasstransfer.2021.120958
References
Ask authors/readers for more resources
Related references
Note: Only part of the references are listed.- Enhanced cooling in compact helical tube cross-flow heat exchanger through higher area density and flow tortuosity
- (2020) Vandana Kumari Jha et al. INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER
- Numerical analysis on the thermal hydraulic effect of wrapped wire spacer in a four rod fuel bundle
- (2019) Attila Kiss et al. NUCLEAR ENGINEERING AND DESIGN
- Turbulent flow and vortex characteristics in a blocked subchannel of a helically wrapped rod bundle
- (2019) Thien Nguyen et al. EXPERIMENTS IN FLUIDS
- Parametric study on heat transfer and pressure drop of twisted oval tube bundle with in line layout
- (2019) Xiuzhen Li et al. INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER
- Comparative study of heat transfer enhancement and pressure drop for fin-and-circular tube compact heat exchangers with sinusoidal wavy and elliptical curved rectangular winglet vortex generator
- (2019) Ashish J. Modi et al. INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER
- High-fidelity velocity measurements in a totally blocked interior subchannel of a wire-wrapped 61-pin hexagonal fuel bundle
- (2019) Thien Nguyen et al. NUCLEAR ENGINEERING AND DESIGN
- CFD and thermal-hydraulics analyses of liquid sodium heat transfer in 19-rod hexagonal bundles with scalloped walls
- (2019) Luis M. Palomino et al. INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER
- One-way coupled simulation of FIV in a 7-pin wire-wrapped fuel pin bundle
- (2019) Landon Brockmeyer et al. NUCLEAR ENGINEERING AND DESIGN
- Stereoscopic PIV measurements of near-wall flow in a tightly packed rod bundle with wire spacers
- (2018) Thien Nguyen et al. EXPERIMENTAL THERMAL AND FLUID SCIENCE
- PTV/PIV measurements of turbulent flows in interior subchannels of a 61-pin wire-wrapped hexagonal fuel bundle
- (2018) Nolan Goth et al. INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW
- Analysis of inter-channel sweeping flow in wire wrapped 19-rod bundle
- (2018) Xi Wang et al. NUCLEAR ENGINEERING AND DESIGN
- The upgraded Cheng and Todreas correlation for pressure drop in hexagonal wire-wrapped rod bundles
- (2018) S.K. Chen et al. NUCLEAR ENGINEERING AND DESIGN
- PIV measurements of turbulent flows in a 61-pin wire-wrapped hexagonal fuel bundle
- (2017) Thien Nguyen et al. INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW
- Experimental study on transient heat transfer across critical pressure in 2 × 2 rod bundle with wire wraps
- (2017) Hong-bo Li et al. INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER
- Pressure Measurements in a Wire-Wrapped 61-Pin Hexagonal Fuel Bundle
- (2017) Rodolfo Vaghetto et al. JOURNAL OF FLUIDS ENGINEERING-TRANSACTIONS OF THE ASME
- Numerical modeling of flow induced vibration of nuclear fuel rods
- (2017) Dante De Santis et al. NUCLEAR ENGINEERING AND DESIGN
- CFD investigation of three-dimensional flow phenomena in a JAEA 127-pin wire-wrapped fuel assembly
- (2017) Jae-Ho Jeong et al. NUCLEAR ENGINEERING AND DESIGN
- Thermal-hydraulic effect of wire spacer in a wire-wrapped fuel bundles for SFR
- (2017) Jae-Ho Jeong et al. NUCLEAR ENGINEERING AND DESIGN
- CFD analysis of transverse flow in a wire-wrapped hexagonal seven-pin bundle
- (2017) Pinghui Zhao et al. NUCLEAR ENGINEERING AND DESIGN
- Heat transfer from a 2 × 2 wire-wrapped rod bundle to supercritical pressure water
- (2016) Han Wang et al. INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER
- Benchmark exercise for fluid flow simulations in a liquid metal fast reactor fuel assembly
- (2016) E. Merzari et al. NUCLEAR ENGINEERING AND DESIGN
- Numerical implementation of the Cheng and Todreas correlation for wire wrapped bundle friction factors-desirable improvements in the transition flow region
- (2013) S.K. Chen et al. NUCLEAR ENGINEERING AND DESIGN
- Evaluation of existing correlations for the prediction of pressure drop in wire-wrapped hexagonal array pin bundles
- (2013) S.K. Chen et al. NUCLEAR ENGINEERING AND DESIGN
- Experimental and numerical study of convective heat transfer and fluid flow in twisted oval tubes
- (2012) Xiang-hui Tan et al. INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER
Discover Peeref hubs
Discuss science. Find collaborators. Network.
Join a conversationFind the ideal target journal for your manuscript
Explore over 38,000 international journals covering a vast array of academic fields.
Search