Search results for " impianti nucleari"

showing 10 items of 413 documents

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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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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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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On the hydraulic behaviour of ITER Shield Blocks #14 and #08. Computational analysis and comparison with experimental tests

2016

Abstract As a consequence of its position and functions, the ITER blanket system will be subjected to significant heat loads under nominal reference conditions. Therefore, the design of its cooling system is particularly demanding. Coolant water is distributed individually to the 440 blanket modules (BMs) through manifold piping, which makes it a highly parallelized system. The mass flow rate distribution is finely tuned to meet all operation constraints: adequate margin to burn out in the plasma facing components, even distribution of water flow among the so-called plasma-facing “fingers” of the Blanket First Wall panels, high enough water flow rate to avoid excessive water temperature in …

Pressure dropPipingComputer scienceWater flowMechanical EngineeringNuclear engineeringFull scaleBlanket CFD analysis HydraulicsBlanket01 natural sciences010305 fluids & plasmasCoolantNuclear Energy and Engineering0103 physical sciencesWater coolingMass flow rateGeneral Materials Science010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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CFD prediction of concentration polarization phenomena in spacer-filled channels for Reverse Electrodialysis

2014

Abstract Salinity Gradient Power generation through Reverse Electrodialysis (SGP-RE) is a promising technology to convert the chemical potential difference of a salinity gradient into electric energy. In SGP-RE systems, as in most membrane processes, concentration polarization phenomena may affect the theoretical driving force and thus the performance of the process. Operating conditions, including the feed solution flow rate and concentration and the channels׳ geometrical configuration, may greatly influence both the polarization effect and the pumping energy consumption. The present work uses CFD to investigate the dependence of concentration polarization and pressure drop on flow rate, f…

Pressure dropSettore ING-IND/26 - Teoria Dello Sviluppo Dei Processi ChimiciChemistryAnalytical chemistryFiltration and Separation02 engineering and technologyElectrodialysis021001 nanoscience & nanotechnology7. Clean energyBiochemistry6. Clean waterVolumetric flow rate020401 chemical engineeringChemical physicsReversed electrodialysisOsmotic powerGeneral Materials Science0204 chemical engineeringPhysical and Theoretical Chemistry0210 nano-technologyPolarization (electrochemistry)Current densitySettore ING-IND/19 - Impianti NucleariConcentration polarizationCFD Reverse Electrodialysis concentration polarization spacer-filled channel mixing promoter
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Steady state and transient thermal–hydraulic analyses on ITER divertor module

2005

Abstract One of the most challenging components of ITER is the divertor devoted at controlling the characteristics of the plasma boundary, exhausting the α particles and reducing the impurities in the plasma. The thermal–hydraulic design of the divertor is particularly, demanding because of the high heat loads and the cooling flow margin in the plasma-facing components (PFCs). The pressure drop is limited by the pumping power and also avoiding the risk of reaching critical heat flux (CHF). Furthermore, for maintenance operation foreseen, each single divertor cassette should be drained and dried before withdrawing it out from the vacuum vessel. To address these requirements, European Fusion …

Pressure dropTokamakMaterials scienceCritical heat fluxHydraulicsMechanical EngineeringNuclear engineeringDivertorFusion powerSteady statelaw.inventionThermal hydraulicsNuclear physicsDivertorTransient thermal–hydraulicNuclear Energy and EngineeringHeat fluxlawITERRELAP codeGeneral Materials ScienceSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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Analysis of Primary/Containment Coupling Phenomena Characterizing the MASLWR Design During a SBLOCA Scenario

2012

Today considering the world energy demand increase, the use of advanced nuclear power plants, have an important role in the environment and economic sustainability of country energy strategy mix considering the capacity of nuclear reactors of producing energy in safe and stable way contributing in cutting the CO2 emission (Bertel & Morrison, 2001; World Energy Outlook-Executive Summary, 2009; Wolde-Rufael & Menyah, 2010; Mascari et al., 2011d). According to the information’s provided by the “Power Reactor Information System” of the International Atomic Energy Agency (IAEA), today 433 nuclear power reactors are in operation in the world providing a total power installed capacity of 366.610 G…

Primary/Containment Coupling MASLWR SBLOCAEnergy demandbusiness.industrySMR MASLWR TRACE Primary/Containment Coupling SBLOCAShutdownAtomic energyNuclear engineeringMASLWRSBLOCANuclear powerNameplate capacityCoupling (computer programming)ContainmentInformation systemPrimary/Containment CouplingEnvironmental sciencebusinessSettore ING-IND/19 - Impianti Nucleari
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An analytical model of heat transfer and fluid dynamic performances of an unconventional NTR engine for manned interplanetary missions

2009

Abstract An analytical model of fluid flow and heat transfer of a Nuclear Thermal Rocket (NTR) engine concept is presented. The engine is based on the direct conversion of the kinetic energy of the fission fragments (FFs) into the propellant enthalpy. The FFs can escape from an extremely thin layer of fissionable material: a sufficiently large surface coated with few micrometers of Americium 242m, confined by a neutron moderator–reflector, may become a critical reactor. Three dimensional coupled CFD-Monte Carlo simulations have already been presented in Di Piazza and Mulas (2006) . In this paper, an analytical integral 1-D model of fluid dynamics and heat transfer is built in order to fores…

PropellantPhysicsNuclear and High Energy PhysicsThermal efficiencyNuclear thermal rocketMechanical EngineeringPéclet numberMechanicssymbols.namesakenon conventional nuclear systemNuclear Energy and Engineeringheat transferHeat transfersymbolsFluid dynamicsGeneral Materials ScienceNeutronSpecific impulseStatistical physicsSafety Risk Reliability and QualityWaste Management and DisposalSettore ING-IND/19 - Impianti NucleariNuclear Engineering and Design
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Modifiche del Codice RELAP5 per lo Studio delle Perdite di Carico in Generatori di Vapore a Tubi Elicoidali Interessati da Flussi Bifase

2010

RELAP5Settore ING-IND/19 - Impianti Nucleari
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