Search results for " impianti nucleari"

showing 10 items of 413 documents

The European contribution to the development and validation activities for the design of IFMIF lithium facility

2013

The International Fusion Materials Irradiation Facility (IFMIF) is an accelerator-driven intense neutron source where candidate materials for fusion reactors will be tested and validated. The high energy neutron flux is produced by means of two deuteron beams (total current of 250 mA, energy of 40 MeV) that strikes a liquid lithium target circulating in a lithium loop of IFMIF plant. The European (EU) contribution to the development of the lithium facility comprises five procurement packages, as follow: (1) participation to the experimental activities of the EVEDA lithium test loop in Oarai (Japan); (2) study aimed at evaluating the corrosion and erosion phenomena, promoted by lithium, for …

Mechanical EngineeringNuclear engineeringLithium testRemote handlingchemistry.chemical_elementInternational Fusion Materials Irradiation FacilityFusion powerLithiumLithium;Remote handling;IFMIF;Corrosion;Target assembly;PurificationCorrosionNuclear Energy and EngineeringchemistryNeutron fluxTarget assemblyIFMIFNeutron sourceEnvironmental scienceGeneral Materials ScienceLithiumPurification methodsEngineering design processSettore ING-IND/19 - Impianti NucleariPurificationCivil and Structural EngineeringIFMIF Target assembly Remote handling Lithium Corrosion Purification
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Large-Eddy Simulation of Turbulent Flow and Heat Transfer in Plane and Rib-Roughened Channels

1992

Large-eddy simulation results are presented and discussed for turbulent flow and heat transfer in a plane channel with and without transverse square ribs on one of the walls. They were obtained with the finite-difference code Harwell-FLOW3D, Release 2, by using the PISOC pressure-velocity coupling algorithm, central differencing in space, and Crank-Nicolson time stepping. A simple Smagorinsky model, with van Driest damping near the walls, was implemented to model subgrid scale effects. Periodic boundary conditions were imposed in the streamwise and spanwise directions. The Reynolds number based on hydraulic diameter (twice the channel height) ranged from 10 000 to 40 000. Results are compar…

MeteorologyComputational MechanicsComputational fluid dynamicsLarge Eddy SimulationPipe flowPhysics::Fluid Dynamicssymbols.namesakeFluid dynamicsHydraulic diameterSettore ING-IND/19 - Impianti NucleariPhysicsbusiness.industryTurbulenceApplied MathematicsMechanical EngineeringReynolds numberFluid DynamicMechanicsHeat TransferComputer Science ApplicationsTurbulenceTransverse planeMechanics of MaterialssymbolsbusinessCFDLarge eddy simulation
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Applicazione del metodo Monte Carlo a problemi monodimensionali di conduzione termica stazionaria in sistemi con conducibilità dipendente dalla posiz…

2010

Metodo MonteCarlo Diffusione termicaSettore ING-IND/19 - Impianti Nucleari
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A multi-physics integrated approach to breeding blanket modelling and design

2019

Abstract Often, for the design of a component, several kinds of analyses are needed. Even more frequently, the different fields of study, to be taken into account for the design verification, have to be examined minutely until the final results are satisfying. Furthermore, when geometry modifications are required, for instance to fulfill the component functions, the analyses cycle has to be restarted and an iterative process has to be carried out. This procedure may be time-consuming and herald of errors, in particular if it is demanded to the human activity. Therefore, it is more convenient for the scientific community to adopt a numerical tool that can combine various computational codes.…

Multi-physicCommercial softwareNeutron transportIterative and incremental developmentHCPBMechanical EngineeringBase (geometry)Blanket7. Clean energy01 natural sciencesWCLL010305 fluids & plasmasCouplingLead (geology)Nuclear Energy and EngineeringCoupling (computer programming)Component (UML)0103 physical sciencesSystems engineeringGeneral Materials ScienceBreeding blanket010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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Thermal-hydraulic and thermal-structural analyses report of DEMO Helium-Cooled Pebble Bed blanket

2012

NUCLEAR FUSION HCPB BLANKETSettore ING-IND/19 - Impianti Nucleari
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Analysis of the thermo-mechanical behaviour of IFMIF-EVEDA Lithium Test Loop Target Assembly

2011

NUCLEAR FUSION IFMIF THERMO-MECHANICSSettore ING-IND/19 - Impianti Nucleari
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Thermo-mechanical issues induced by neutron swelling in the IFMIF Target Assembly back-plate

2011

NUCLEAR FUSION NEUTRON SWELLING IFMIFSettore ING-IND/19 - Impianti Nucleari
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On the investigation of Lithium Methatitanate pebble bed thermal diffusive properties by the Improved Current Pulse method

2012

NUCLEAR FUSION PEBBLE BED LITHIUM METHATITANATESettore ING-IND/19 - Impianti Nucleari
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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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Thermal-hydraulic and thermal-structural analyses report of DEMO WCLL blanket

2012

NUCLEAR FUSION WCLL BLANKETSettore ING-IND/19 - Impianti Nucleari
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