Search results for " impianti nucleari"

showing 10 items of 413 documents

Thermal-hydraulic and thermo-mechanical simulations of Water-Heavy Liquid Metal interactions towards the DEMO WCLL breeding blanket design

2019

Abstract The Water-Cooled Lithium Lead breeding blanket concept foresees the eutectic lithium-lead (Pb-15.7Li) alloy being cooled by pressurized sub-cooled water (temperature 295–328 °C; pressure 15.5 MPa) flowing in double wall tubes. Therefore, the interaction between the Pb-15.7Li and water (e.g. tube rupture) represents one of the main safety concerns for the design and safety analysis. Available LIFUS5/Mod2 experimental data are employed to assess the performances of thermal-hydraulic and thermo-mechanic codes. Thermal-hydraulic simulations, by SIMMER-III code, are focused on the prediction of the thermodynamic interaction among the fluids. ABAQUS Finite Element code, used for the desi…

Liquid metalMaterials scienceNuclear engineeringchemistry.chemical_elementBlanket01 natural sciences010305 fluids & plasmasThermal hydraulics0103 physical sciencesGeneral Materials ScienceTube (fluid conveyance)010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringEutectic systemMechanical EngineeringStress–strain curveWater-Liquid metal interactionExperimental dataBreeding blanket; LIFUS5; Water-Liquid metal interactionsWater-Liquid metal interactionsNuclear Energy and EngineeringchemistryLithiumBreeding blanketLIFUS5
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Assessment of the Thermo-mechanical Performances of a DEMO Water-Cooled Liquid Metal Blanket Module

2015

Within the framework of DEMO R&D activities, a research cooperation has been launched between ENEA-Brasimone, CEA-Saclay and the University of Palermo to investigate the thermo-mechanical behaviour of the outboard equatorial module of the DEMO1 Water-Cooled Lithium Lead (WCLL) blanket, both under normal operation and over-pressurization steady state scenarios. The research campaign has been carried out following a theoretical-computational approach based on the finite element method (FEM) and adopting a qualified commercial FEM code. In particular, two different three-dimensional FEM models of the WCLL blanket module have been set-up to be used for normal operation and over-pressurization a…

Liquid metalNuclear and High Energy PhysicsMaterials science[PHYS.NUCL]Physics [physics]/Nuclear Theory [nucl-th]Nuclear engineeringDEMO reactorBlanket[PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]01 natural sciences7. Clean energyThermo-mechanics;DEMO reactor;WCLL blanket010305 fluids & plasmasBreeder (animal)0103 physical sciencesThermal010306 general physicsSettore ING-IND/19 - Impianti NucleariSteady stateToroidThermo-mechanicsThermo-mechanic6. Clean waterFinite element methodCoolantWCLL blanketNuclear Energy and Engineering
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Progress in the benchmark exercise for analyzing the lithiate breeder pebble bed thermo-mechanical behaviour

2006

The Helium Cooled Pebble Bed (HCPB) Blanket is one of the reference concepts for the European Breeding Blanket Programme for DEMO. In the reference blanket module, alternate layers of lithiated ceramics and beryllium pebbles act, respectively, as tritium breeder and neutron multiplier. The thermo-mechanical behaviour of both the pebble beds and their performances in reactor relevant conditions are also dependent on the pebble size and cell geometries (bed thickness, pebble packing factor, bed thermal conductivity). Therefore, in the EU Fusion Technology Programme, several out-of-pile experimental test campaigns have been performed to determine these behaviours. Theoretical calculations have…

Lithiated ceramicMechanical EngineeringNuclear engineeringchemistry.chemical_elementBlanketFusion powerBreederAtomic packing factorCalculation methodsThermo-mechanical behaviourNuclear Energy and EngineeringchemistryThermal mechanicalGeneral Materials ScienceBerylliumPebbleSettore ING-IND/19 - Impianti NucleariThermo mechanicalCivil and Structural EngineeringFusion Engineering and Design
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Natural Convection in Liquid Metal-Filled Rectangular Enclosures with Volumetric Heating

1998

Low Prandtl number FluidNatural ConvectionRectangular EnclosureCFDLiquid MetalSettore ING-IND/19 - Impianti NucleariInternal Heating
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Analysis of the OSU-MASLWR Natural circulation phenomena using TRACE code

2009

MASLWR TRACE Code Small Modular ReactorSettore ING-IND/19 - Impianti Nucleari
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Analyses of the OSU-MASLWR Natural Circulation Phenomena By Using TRACE Code

2012

MASLWRSettore ING-IND/19 - Impianti Nucleari
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TRACE, RELAP5 Mod 3.3, and RELAP5-3D Code Comparison of OSU-MASLWR-001 Test

2009

MASLWRTRACE code Smal Modular ReactorSettore ING-IND/19 - Impianti Nucleari
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Electrodialysis with asymmetrically profiled membranes: Influence of profiles geometry on desalination performance and limiting current phenomena

2021

Abstract Electrodialysis (ED) has recently gained much attention in the wide field of desalination and water treatment. However, energy consumption and capital costs may impair the process competitiveness. In this regard, limiting current density (LCD) and current efficiency (η) are key performance parameters for optimized ED systems. In this work, an experimental campaign was carried out characterizing the performance of ED stacks when adopting asymmetrically profiled membranes. Current–voltage curves were recorded under different operating conditions mimicking the operation of brackish water or seawater desalination units. Results showed that there was a preferable direction of the electr…

Mass transportSettore ING-IND/26 - Teoria Dello Sviluppo Dei Processi ChimiciMaterials scienceCurrent utilizationGeneral Chemical Engineering02 engineering and technologyDesalination020401 chemical engineeringCorrugated membraneGeneral Materials Science0204 chemical engineeringComposite materialSettore ING-IND/19 - Impianti NucleariIon exchange membraneWater Science and TechnologyPolarization phenomenaMechanical EngineeringLimiting currentGeneral ChemistryElectrodialysis021001 nanoscience & nanotechnologyMembraneBrineWater treatmentElectric currentCurrent (fluid)0210 nano-technologyDesalination
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On the adoption of the Monte Carlo method to solve one-dimensional steady state thermal diffusion problems for non-uniform solids

2013

Abstract The present paper is focussed on the investigation of the potential adoption of the Monte Carlo method to solve one-dimensional, steady state, thermal diffusion problems for continuous solids characterised by an isotropic, space-dependent conductivity tensor and subjected to non-uniform heat power deposition. To this purpose the steady state form of Fourier’s heat diffusion equation relevant to a continuous, heterogeneous and isotropic solid, undergoing a space-dependent heat power density has been solved in a closed analytical form for the general case of Cauchy’s boundary conditions. The thermal field obtained has been, then, put in a peculiar functional form, indicating that it …

Materials scienceApplied MathematicsQuantum Monte CarloMonte Carlo methodThermal diffusivityModeling and SimulationIsotropic solidDynamic Monte Carlo methodMonte Carlo method Heat diffusion Space-dependent thermal conductivityDiffusion Monte CarloHeat equationStatistical physicsSettore ING-IND/19 - Impianti NucleariMonte Carlo molecular modeling
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Thermal–mechanical and thermal–hydraulic integrated study of the Helium-Cooled Lithium Lead Test Blanket Module

2010

Abstract The Helium-Cooled Lithium Lead Test Blanket Module (HCLL-TBM) is one of the two TBM to be installed in an ITER equatorial port since day 1 of operation, with the specific aim to investigate the main concept functionalities and issues such as high efficiency helium cooling, resistance to thermo-mechanical stresses, manufacturing techniques, as well as tritium transport, magneto-hydrodynamics effects and corrosion. In particular, in order to show a DEMO-relevant thermo-mechanical and thermal–hydraulic behavior, the HCLL-TBM has to meet several requirements especially as far as its coolant thermofluid-dynamic conditions and its thermal–mechanical field are concerned. The present paper…

Materials scienceConvective heat transferMechanical EngineeringNuclear engineeringHCLL TBM Thermal-mechanical analysesThermal contactBlanketThermal conductionCoolantThermal hydraulicsNuclear Energy and EngineeringHeat fluxHeat transferGeneral Materials ScienceSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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