Experimental characterization of pressure and friction factor in an interior subchannel of a 61-pin wire-wrapped rod bundle with a porous blockage
出版年份 2023 全文链接
标题
Experimental characterization of pressure and friction factor in an interior subchannel of a 61-pin wire-wrapped rod bundle with a porous blockage
作者
关键词
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出版物
PHYSICS OF FLUIDS
Volume 35, Issue 11, Pages -
出版商
AIP Publishing
发表日期
2023-11-06
DOI
10.1063/5.0175227
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注意:仅列出部分参考文献,下载原文获取全部文献信息。- Experimental study on the effect of throat length on the dynamics of internal unsteady cavitating flow
- (2023) P K Ullas et al. PHYSICS OF FLUIDS
- Flow characteristics within an interior subchannel of a 61-pin wire-wrapped hexagonal rod bundle with a porous blockage
- (2023) Craig Menezes et al. PHYSICS OF FLUIDS
- Flow field characteristics of a 127-pin rod bundle with hexagonal spacer grids
- (2023) Craig Menezes et al. PHYSICS OF FLUIDS
- Validation of RANS simulations on a 61-pin wire-wrapped fast-reactor fuel assembly under the presence of localized blockages
- (2023) Octavio Bovati et al. NUCLEAR ENGINEERING AND DESIGN
- Experimental and numerical investigation on the wake flow and vortex shedding of a rotating circular cylinder
- (2023) Jianhan Liu et al. PHYSICS OF FLUIDS
- Experimental analysis of temperature and vapor core pressure for an annular heat pipe
- (2023) Daniel Orea et al. PHYSICS OF FLUIDS
- Thermal‐hydraulic analysis of wire‐wrapped rod bundle in lead‐based fast reactor with non‐uniform heat flux
- (2022) Kejian Dong et al. INTERNATIONAL JOURNAL OF ENERGY RESEARCH
- The blockage model of Upgraded Cheng and Todreas correlation for pressure drop in hexagonal wire-wrapped rod bundles
- (2022) Y.M. Chen et al. NUCLEAR ENGINEERING AND DESIGN
- Analysis of the turbulent flow in a partially blocked wire-wrapped rod bundle using LES with wall functions
- (2022) Octavio Bovati et al. INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW
- Experimental measurements of fluid flow in an 84-pin hexagonal rod bundle with spacer grid for a gas-cooled fast modular reactor
- (2022) Camila Freitas Matozinhos et al. INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW
- Numerical analysis of the three-dimensional flow phenomena in a 19-pin wire-wrapped tight lattice bundle
- (2022) Junlong Li et al. INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER
- Implementation of a CFD methodology for computing subchannel friction factors and split parameters in wire-wrapped rod bundles
- (2022) Octavio Bovati et al. NUCLEAR ENGINEERING AND DESIGN
- Prediction of flow regime boundary and pressure drop for hexagonal wire-wrapped rod bundles using artificial neural networks
- (2022) Hansol Kim et al. PHYSICS OF FLUIDS
- Experimental study of coherent wall-pressure fluctuations associated with the turbulent near wake of a cylinder
- (2022) R. H. Hernández PHYSICS OF FLUIDS
- Experimental determination and analysis of the transverse pressure difference in a wire-wrapped rod bundle
- (2021) Mason Childs et al. INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER
- Advanced flow and temperature measurements in a forced convection molten salt test loop
- (2021) Ojasvin Arora et al. ANNALS OF NUCLEAR ENERGY
- RANS simulations for transition and turbulent flow regimes in wire-wrapped rod bundles
- (2021) Octavio Bovati et al. INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW
- Prediction of pressure drop in hexagonal wire-wrapped rod bundles using artificial neural network
- (2021) Hansol Kim et al. NUCLEAR ENGINEERING AND DESIGN
- Pressure drop and flow characteristics in partially blocked wire wrapped rod bundles
- (2021) Octavio Bovati et al. ANNALS OF NUCLEAR ENERGY
- Experimental Investigation of the Subchannel Axial Pressure Drop and Hydraulic Characteristics of a 61-Pin Wire Wrapped Rod Bundle
- (2021) Craig Menezes et al. JOURNAL OF FLUIDS ENGINEERING-TRANSACTIONS OF THE ASME
- Analysis of pressure losses and flow distribution in wire-wrapped hexagonal rod bundles for licensing. Part I: The Pacio-Chen-Todreas Detailed model (PCTD)
- (2021) J. Pacio et al. NUCLEAR ENGINEERING AND DESIGN
- Analysis of pressure losses and flow distribution in wire-wrapped hexagonal rod bundles for licensing. Part II: Evaluation of public experimental data
- (2021) J. Pacio et al. NUCLEAR ENGINEERING AND DESIGN
- An experiment study of pressure drop and flow distribution in subchannels of a 37-pin wire-wrapped rod bundle
- (2020) Yu Liang et al. APPLIED THERMAL ENGINEERING
- Experimental investigation of turbulent wake flows in a helically wrapped rod bundle in presence of localized blockages
- (2020) T. Nguyen et al. PHYSICS OF FLUIDS
- Experimental Study on the Effect of Localized Blockages on the Friction Factor of a 61-Pin Wire-Wrapped Bundle
- (2020) Mason Childs et al. JOURNAL OF FLUIDS ENGINEERING-TRANSACTIONS OF THE ASME
- Numerical Study on the Thermal Hydraulic Characteristics in a Wire-Wrapped Assembly of LFRs
- (2020) Jun Li et al. Frontiers in Energy Research
- A porous medium model for simulating conjugate heat transfer between wire-wrapped fuel bundles under forced and mixed convection
- (2020) Yutong Chen et al. ANNALS OF NUCLEAR ENERGY
- CFD analysis of flow blockage phenomena in a LBE-cooled 19-pin wire-wrapped rod bundle
- (2019) Xiang Chai 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
- Experimental investigation on the influence of gap vortex streets on fluid-structure interactions in hexagonal bundle geometries
- (2019) F. Bertocchi et al. INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW
- Direct Numerical Simulation of the Flow Through a Randomly Packed Pebble Bed
- (2019) Mustafa Alper Yildiz et al. JOURNAL OF FLUIDS ENGINEERING-TRANSACTIONS OF THE ASME
- Blockage fuel pin simulator experiments and simulation
- (2019) R. Marinari et al. NUCLEAR ENGINEERING AND DESIGN
- 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
- Towards validated prediction with RANS CFD of flow and heat transport in a wire-wrap fuel assembly
- (2019) Ferry Roelofs et al. NUCLEAR ENGINEERING AND DESIGN
- Understanding migratory flow caused by helicoid wire spacers in rod bundles: An experimental and theoretical study
- (2019) F. Bertocchi et al. INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW
- Analysis of flow and heat transfer through a partially blocked fuel subassembly of fast breeder reactor
- (2019) Madhusree Sarkar et al. PROGRESS IN NUCLEAR ENERGY
- Numerical investigation of flow blockage accident in SFR fuel assembly
- (2019) Xiang Chai 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
- Heat transfer experiment in a partially (internally) blocked 19-rod bundle with wire spacers cooled by LBE
- (2018) J. Pacio 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
- Investigations on thermal hydraulic consequences of planar blockage in a prototype sodium cooled fast reactor fuel subassembly
- (2018) M. Naveen Raj et al. PROGRESS IN NUCLEAR ENERGY
- Comparison of experimental and simulation results on interior subchannels of a 61-pin wire-wrapped hexagonal fuel bundle
- (2018) N. Goth 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
- 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 simulations for determination of minimum representative bundle size in wire wrapped tube bundles
- (2017) Landon Brockmeyer et al. NUCLEAR ENGINEERING AND DESIGN
- RANS based CFD methodology for a real scale 217-pin wire-wrapped fuel assembly of KAERI PGSFR
- (2017) Jae-Ho Jeong et al. NUCLEAR ENGINEERING AND DESIGN
- Laser-Doppler measurements of the turbulent mixing of two rectangular water jets impinging on a stationary pool
- (2016) Huhu Wang et al. INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER
- Flow Distribution and Pressure Loss in Subchannels of a Wire-Wrapped 37-pin Rod Bundle for a Sodium-Cooled Fast Reactor
- (2016) Seok-Kyu Chang et al. Nuclear Engineering and Technology
- Turbulent flow around a square cylinder at Reynolds number 22,000: A DNS study
- (2015) F.X. Trias et al. COMPUTERS & FLUIDS
- A review of inherent safety characteristics of metal alloy sodium-cooled fast reactor fuel against postulated accidents
- (2015) Tanju Sofu Nuclear Engineering and Technology
- Thermal hydraulic effect of porous blockage in fuel subassembly of sodium cooled fast reactor
- (2014) N. Govindha Rasu et al. ANNALS OF NUCLEAR ENERGY
- Two-point statistics for turbulent boundary layers and channels at Reynolds numbers up to δ+ ≈ 2000
- (2014) Juan A. Sillero et al. PHYSICS OF FLUIDS
- A momentum source model for wire-wrapped rod bundles—Concept, validation, and application
- (2013) Rui Hu et al. NUCLEAR ENGINEERING AND DESIGN
- Thermal–hydraulic analysis of wire-wrapped SFR test subassemblies by subchannel analysis method
- (2012) Syeilendra Pramuditya et al. ANNALS OF NUCLEAR ENERGY
- Generalized Morse Wavelets as a Superfamily of Analytic Wavelets
- (2012) J. M. Lilly et al. IEEE TRANSACTIONS ON SIGNAL PROCESSING
- Measured wavenumber: Frequency spectrum associated with acoustic and aerodynamic wall pressure fluctuations
- (2010) Blandine Arguillat et al. JOURNAL OF THE ACOUSTICAL SOCIETY OF AMERICA
- Turbulent flow simulation in a wire-wrap rod bundle of an LMFBR
- (2010) K. Natesan et al. NUCLEAR ENGINEERING AND DESIGN
- The thermal hydraulics in a rod bundle representative of the start-up core of the ALLEGRO Gas cooled Fast Reactor—Experimental and numerical approaches
- (2010) Marc Berthoux et al. NUCLEAR ENGINEERING AND DESIGN
- Analysis of three different types of blockage in a sodium flow path with the MATRA-LMR-FB code
- (2009) H.-Y. Jeong et al. ANNALS OF NUCLEAR ENERGY
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