Search results for "Pressure drop"

showing 10 items of 57 documents

Experimental Analysis of Local Pressure Losses for Microirrigation Laterals

2004

The accurate design of drip irrigation laterals needs to consider the variation of hydraulic head due to pipe elevation changes, head losses along the lines, and also, at a given operating pressure, emitter discharge variations related to manufacturing variability, clogging, and water temperature. Hydraulic head variations are consequent to both the friction losses and local losses due to the in-line or on-line emitters along the pipe, which determine the contraction and subsequent enlargement of the flow streamlines. Moreover, in-line emitters usually have a smaller diameter than the pipe, and therefore an additional friction loss must be considered. Evaluation of energy losses and consequ…

Pressure dropEngineeringbusiness.industryeducationReynolds numberLow-flow irrigation systemsDrip irrigationMechanicsAgricultural and Biological Sciences (miscellaneous)Friction lossPhysics::Fluid Dynamicssymbols.namesakeHydraulic headsymbolsPhysics::Accelerator PhysicsHead (vessel)Geotechnical engineeringStreamlines streaklines and pathlinesbusinessWater Science and TechnologyCivil and Structural EngineeringJournal of Irrigation and Drainage Engineering
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Analysis of the steady state hydraulic behaviour of the ITER blanket cooling system

2015

Abstract The blanket system is the ITER reactor component devoted to providing a physical boundary for plasma transients and contributing to thermal and nuclear shielding of vacuum vessel, magnets and external components. It is expected to be subjected to significant heat loads under nominal conditions and its cooling system has to ensure an adequate cooling, preventing any risk of critical heat flux occurrence while complying with pressure drop limits. At the University of Palermo a study has been performed, in cooperation with the ITER Organization, to investigate the steady state hydraulic behaviour of the ITER blanket standard sector cooling system. A theoretical–computational approach …

Pressure dropFinite volume methodSteady stateITER Blanket HydraulicsCritical heat fluxMechanical EngineeringMass flowNuclear engineeringBlanketCoolantNuclear Energy and EngineeringWater coolingEnvironmental scienceGeneral Materials ScienceSettore ING-IND/19 - Impianti NucleariCivil and Structural Engineering
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On the influence of curvature and torsion on turbulence in helically coiled pipes

2014

Turbulent flow and heat transfer in helically coiled pipes at Ret=400 was investigated by DNS using finite volume grids with up to 2.36×10^7 nodes. Two curvatures (0.1 and 0.3) and two torsions (0 and 0.3) were considered. The flow was fully developed hydrodynamically and thermally. The central discretization scheme was adopted for diffusion and advection terms, and the second order backward Euler scheme for time advancement. The grid spacing in wall units was ~3 radially, 7.5 circumferentially and 20 axially. The time step was equal to one viscous wall unit and simulations were typically protracted for 8000 time steps, the last 4000 of which were used to compute statistics. The results sho…

Pressure dropHistoryFinite volume methodDirect Numerical SimulationTurbulencehelically coiled pipeTorsion (mechanics)GeometrySecondary flowCurvatureNusselt numberComputer Science ApplicationsEducationTurbulencePhysics::Fluid DynamicsHeat transferSettore ING-IND/19 - Impianti NucleariMathematicsJournal of Physics: Conference Series
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Liquid metal MHD experimental activities for LLCB TBM development

2013

Abstract In Indian Lead Lithium cooled Ceramic Breeder (LLCB) blanket concept, Lead–Lithium (Pb–Li) liquid metal is used to extract heat from its own bulk volume and also from the neighboring solid breeder zones. The moderate flow velocity of Pb–Li inside the module can be significantly modified due to MHD effects, which arise because of the presence of strong toroidal magnetic field. Recently, two MHD experiments have been jointly carried out at Institute of Physics, University of Latvia (IPUL) with hot Pb–Li (∼350 C) as the working fluid under a strong transverse magnetic field of up to ∼4.0 T. The uncoated test sections are made of SS316L material and consist of LLCB TBM relevant flow ge…

Pressure dropLiquid metalMaterials scienceMechanical EngineeringFluid mechanicsMechanicsBlanketBreeder (animal)Nuclear Energy and EngineeringFlow velocityWorking fluidGeneral Materials ScienceMagnetohydrodynamicsCivil and Structural EngineeringFusion Engineering and Design
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Liquid metal MHD studies with non-magnetic and ferro-magnetic structural material

2014

Abstract In most of the liquid metal MHD experiments reported in the literature to study liquid breeder blanket performance, SS316/SS304 grade steels are used as the structural material which is non-magnetic. On the other hand, the structural material for fusion blanket systems has been proposed to be ferritic martensitic grade steel (FMS) which is ferromagnetic in nature. In the recent experimental campaign, liquid metal MHD experiments have been carried out with two identical test sections: one made of SS316L (non-magnetic) and another with SS430 (ferromagnetic), to compare the effect of structural materials on MHD phenomena for various magnetic fields (up to 4 T). The maximum Hartmann nu…

Pressure dropLiquid metalMaterials scienceMechanical EngineeringMechanicsBlanketHartmann numberMagnetic fieldNuclear Energy and EngineeringFerromagnetismPerpendicularGeneral Materials ScienceMagnetohydrodynamicsCivil and Structural EngineeringFusion Engineering and Design
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Numerical and experimental MHD studies of Lead-Lithium liquid metal flows in multichannel test-section at high magnetic fields

2018

Abstract Numerical simulation and experiments have been performed at high magnetic fields (1–3T) to study the MHD assisted molten Lead-Lithium (PbLi) flow in a model test-section which has typical features of multiple parallel channel flows as foreseen in various blanket module of ITER. The characteristics Hartmann number of the presented case study is up to 1557 which is relevant to typical fusion blanket conditions. Symbols B0, a, σ, μ in the definition of Hartmann number are strength of the applied magnetic field, characteristic length scale which is half the channel width parallel to the magnetic field, electrical conductivity and dynamic viscosity of PbLi respectively. Flow distributio…

Pressure dropMaterials scienceCharacteristic lengthMechanical EngineeringLaminar flowMechanicsHartmann number01 natural sciences010305 fluids & plasmasMagnetic fieldVolumetric flow ratePhysics::Fluid DynamicsNuclear Energy and EngineeringFlow (mathematics)0103 physical sciencesGeneral Materials ScienceMagnetohydrodynamics010306 general physicsCivil and Structural EngineeringFusion Engineering and Design
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Fully developed laminar flow and heat transfer in serpentine pipes

2015

Abstract A serpentine pipe is a sequence of parallel straight pipe segments connected by U-bends. Its geometry is fully characterized by pipe radius, a , bend curvature radius, c and length of the straight segments, l . The repeated curvature inversion forces the recirculation (secondary flow) pattern to switch between two specular configurations, which may enhance mixing and heat or mass transfer with respect to a constant-curvature pipe at the cost of an increase in pressure drop. In the present work, fully developed laminar flow and heat transfer in serpentine pipes were investigated by numerical simulation. The curvature δ  =  a / c was made to vary between 0.1 and 0.5 while the paramet…

Pressure dropMaterials sciencePrandtl numberGeneral EngineeringCurved pipeReynolds numberLaminar flowMechanicsSerpentine pipeStokes flowComputational fluid dynamicsCondensed Matter PhysicsCurvatureNusselt numberPhysics::Fluid Dynamicssymbols.namesakeHeat transfersymbolsU bendSecondary flowSettore ING-IND/19 - Impianti Nucleari
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Chemical compatibility of bulk alumina in flowing PbLi alloy under magnetic field

2021

Abstract Electrically insulating flow channel inserts (FCI) may be needed in liquid-based breeding blanket concepts to electrically decouple the metal flow from the strong magnetic field in a future fusion reactor. Although the magnetohydrodynamic simulation demonstrates a reduction of the pressure drop when a sandwich-like steel-alumina-steel FCI is employed, the tritium production efficiency in the breeding zone of a breeding blanket is limited to 550 °C due to the steel corrosion. Previous theoretical thermomechanical analyses point out the possible occurrence of induced interfacial stresses between the steel and the ceramic part. Both factors motivate the actual FCI development towards …

Pressure dropMaterials scienceScanning electron microscopeMechanical EngineeringAlloyInsulator (electricity)Fusion powerBlanketengineering.material01 natural sciences010305 fluids & plasmasCorrosionNuclear Energy and Engineeringvisual_art0103 physical sciencesvisual_art.visual_art_mediumengineeringGeneral Materials ScienceCeramicComposite material010306 general physicsCivil and Structural EngineeringFusion Engineering and Design
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Numerical prediction of turbulent flow and heat transfer in helically coiled pipes

2010

Abstract Computational results were obtained for turbulent flow and heat transfer in curved pipes, representative of helically coiled heat exchangers. Following a grid refinement study, grid independent predictions from alternative turbulence models ( k – ɛ , SST k – ω and RSM– ω ) were compared with DNS results and experimental pressure drop and heat transfer data. Using the SST k – ω and RSM– ω models, pressure drop results were in excellent agreement with literature data and the Ito correlation. For heat transfer, the literature is not comparably complete or accurate, but a satisfactory agreement was obtained in the range of available data. Unsatisfactory results, both for pressure drop …

Pressure dropMaterials scienceTurbulenceGeneral EngineeringTurbulence modelingThermodynamicsReynolds stressCondensed Matter PhysicsChurchill–Bernstein equationNusselt numberHeat transferHeat exchangerhelically coiled tubes curved tubes pressure drop heat transfer turbulent flow turbulence modelsSettore ING-IND/19 - Impianti NucleariInternational Journal of Thermal Sciences
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ICONE19-43144 RELAP5 SIMULATION OF TWO-PHASE FLOW EXPERIMENTS IN VERTICAL HELICAL TUBES

2011

Pressure dropMaterials sciencemedicine.anatomical_structuremedicineTwo-phase flowMechanicsIris (anatomy)The Proceedings of the International Conference on Nuclear Engineering (ICONE)
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