Search results for "hydraulics"

showing 10 items of 86 documents

Further experiences on unsteady seepage flow

1973

The present paper describes the results of a study on the unsteady flow in a horizontal homogeneous filter, which is accomplished when the level of the reservoir that recharges the filter is instantly drawn up. This study was carried out at the University of Palermo Institute of Hydraulics as a part of a research program concerning artificial recharge of ground water and the geotechnical problems involving the stability of porous media subject to the variations of surrounding pressures. A numerical procedure, aiming at solving the equation of Boussinesq by a finite difference method, was adopted and an electronic computer was used. A Hele-Shaw filter model was used to carry out several expe…

Mathematical modelComputer scienceHydraulicsMechanical EngineeringFinite difference methodMechanicsGroundwater rechargeCondensed Matter PhysicsStability (probability)law.inventionFilter (large eddy simulation)Mechanics of MaterialslawFluid dynamicsPorous mediumMeccanica
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On a computational study of the hydraulic behavior of the ITER divertor cassette full-scale prototype

2009

NUCLEAR FUSION DIVERTOR THERMAL-HYDRAULICS
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Hydraulic Analysis of the CDR Design of the ITER TBM Port Plug

2013

NUCLEAR FUSION TBM PORT PLUG THERMAL-HYDRAULICSSettore ING-IND/19 - Impianti Nucleari
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Analyses of single- and two-phase flow pressure drops in helical pipes using a modified RELAP5 code

2012

Abstract Thermal fluid dynamics analyses on single- and two-phase flows in helical pipes of steam generators to be used in Generation III and IV nuclear reactors have been performed. The study concerned with experimental activities as well code simulations carried out in the framework of a collaboration between the Department of Energetics of the Polytechnic of Torino and the Department of Energy of the University of Palermo. The goal was the validation of models implemented in Relap5/Mod3.2β thermal–hydraulic advanced code to simulate the hydrodynamic behaviour of helical pipe components in spite of the one-dimensional nature of the code. It is shown that much of the experimental data obta…

Nuclear and High Energy PhysicsEngineeringHydraulicsNuclear engineeringMechanical engineeringReattori nucleari innovativiGeneratori di vapore elicoidalilaw.inventionThermal hydraulicsTUBESlawThermalFluid dynamicsCode (cryptography)General Materials ScienceSafety Risk Reliability and QualityWaste Management and DisposalSettore ING-IND/19 - Impianti NucleariTWO PHASEPressure dropbusiness.industryMechanical EngineeringRELAP5/MOD3.2Fluid mechanicsGeneratori di vapore elicoidali; Reattori nucleari innovativiNuclear Energy and EngineeringHELICOIDAL PIPESTwo-phase flowbusiness
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Sensitivity Analysis of the MASLWR Helical Coil Steam Generator Using TRACE

2011

Accurate simulation of transient system behavior of a nuclear power plant is the goal of systems code calculations, and the evaluation of a code's calculation accuracy is accomplished by assessment and validation against appropriate system data. These system data may be developed either from a running system prototype or from a scaled model test facility, and characterize the thermal hydraulic phenomena during both steady state and transient conditions. The identification and characterization of the relevant thermal hydraulic phenomena, and the assessment and validation of thermal hydraulic systems codes, has been the objective of multiple international research programs. The validation and…

Nuclear and High Energy PhysicsEngineeringbusiness.industryMechanical EngineeringSuperheated steamNuclear engineeringNuclear Engineering Thermal HydraulicBoiler (power generation)System safetyNuclear reactorlaw.inventionThermal hydraulicsNatural circulationNuclear Energy and EngineeringNuclear reactor corelawHeat exchangerForensic engineeringGeneral Materials ScienceSafety Risk Reliability and QualitybusinessWaste Management and DisposalSettore ING-IND/19 - Impianti NucleariTRACE Code MASLWR SMR Helical Coils Steam Generator Natural Circulation
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On the numerical assessment of the thermal-hydraulic operating map of the DEMO Divertor Plasma Facing Components cooling circuit

2020

Abstract Within the framework of the Work Package DIV 1 - “Divertor Cassette Design and Integration” of the EUROfusion action, a research campaign has been jointly carried out by University of Palermo and ENEA to investigate the thermal-hydraulic behaviour of the DEMO divertor cassette cooling system, focussing the attention on the 2018 configuration of the Plasma Facing Components (PFCs) circuit consistent with the DEMO baseline 2017. The research campaign has been carried out following a theoretical-computational approach based on the finite volume method and adopting the commercial Computational Fluid-Dynamic (CFD) code ANSYS CFX. A steady-state CFD analysis has been carried out for the …

Nuclear engineeringComputational fluid dynamics01 natural sciences010305 fluids & plasmasThermal hydraulicsDivertor0103 physical sciencesMass flow rateWater coolingGeneral Materials ScienceTotal pressure010306 general physicsDEMOPlasma facing componentsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringThermofluid-dynamicsCritical heat fluxbusiness.industryMechanical EngineeringDivertorCoolantNuclear Energy and EngineeringEnvironmental sciencebusinessCFD analysisFusion Engineering and Design
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On the thermal-hydraulic optimization of DEMO divertor plasma facing components cooling circuit

2018

Abstract Within the framework of the Work Package Divertor, Subproject: Cassette Design and Integration (WPDIV-Cassette) of the EUROfusion action, a research campaign has been jointly carried out by ENEA and University of Palermo to investigate the thermal-hydraulic performances of the DEMO divertor cassette cooling system. Attention has been focussed on the divertor Plasma Facing Components (PFCs) cooling circuit and a parametric analysis has been carried out in order to assess the potential impact of proper layout changes on its thermal-hydraulic performances, mainly in terms of coolant total pressure drop, flow velocity distribution and margin against critical heat flux occurrence. The r…

Nuclear engineeringComputational fluid dynamicsThermofluid-dynamic01 natural sciences7. Clean energy010305 fluids & plasmasThermal hydraulicsDivertor0103 physical sciencesWater coolingGeneral Materials ScienceCFD analysi010306 general physicsDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFinite volume methodCritical heat fluxbusiness.industryDivertorMechanical EngineeringPlasma facing componentCoolantFlow velocityNuclear Energy and EngineeringEnvironmental scienceMaterials Science (all)businessFusion Engineering and Design
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Explicit relationships for optimal designing rectangular microirrigation units on uniform slopes: The IRRILAB software application

2018

Abstract Many attempts have been made to provide easy tools for designing microirrigation units. However, most of these have dealt with numerical solutions, which require many trial-and-error attempts and time-consuming iterations, performed by applying the basic hydraulic equations from the manifold to the end of both the downhill and the uphill sides of the laterals. Recently, analytical procedures to optimally design paired drip laterals on uniform slopes were proposed, providing readily obtainable results and energy saving. Although these analytical solutions can be practically applied, they only make it possible to design a one-lateral unit; to be really interesting for practical appli…

Optimal designMathematical optimizationComputer scienceHydraulics0208 environmental biotechnology02 engineering and technologyHorticulturelaw.inventionPipe network analysissymbols.namesakeSoftwarelawOptimal design relationshipSettore AGR/08 - Idraulica Agraria E Sistemazioni Idraulico-ForestaliEnergy-savingDrip irrigation unitbusiness.industryIRRILAB software applicationDesign toolReynolds numberForestryComputer Science Applications1707 Computer Vision and Pattern Recognition020801 environmental engineeringComputer Science ApplicationssymbolsbusinessMicroirrigationManifold (fluid mechanics)RowAgronomy and Crop Science
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Mass Estimation of Self-Contained Linear Electro-Hydraulic Actuators and Evaluation of the Influence on Payload Capacity of a Knuckle Boom Crane

2019

Abstract Self-contained linear hydraulic drives are characterized by having integrated the hydraulic power unit e.g. electrical prime mover, hydraulic pumps etc. and the hydraulic cylinder in a single compact unit. Compared to the hydraulic cylinder itself, the mass of the self-contained linear actuator is significantly larger. For some applications, e.g. crane manipulators the additional mass of the actuators compared to conventional valve-controlled hydraulics, may reduce the payload capacity, which is a central performance parameter. As a case study, a medium sized two link knuckle boom crane is modelled and by assuming the force capability of the hydraulic cylinders to be the limiting f…

PayloadHydraulicsComputer scienceElectro hydraulicBoomlaw.inventionHydraulic cylinderKnucklemedicine.anatomical_structurelawmedicineActuatorHydraulic pumpMarine 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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