Search results for "Structural engineering"

showing 10 items of 1998 documents

TRITIUM RELEASE CHARACTERISTICS OF NEUTRON-IRRADIATED REFERENCE BERYLLIUM PEBBLES FOR THE HELIUM COOLED PEBBLE BED (HCPB) BLANKET

2011

In this paper, we present results on tritium release from the beryllium pebbles irradiated for 294 full power days from 17 April 2003 to November 2004 to the neutron fluence of 1.5-2 × 1025 m-2 (E>...

Nuclear and High Energy PhysicsMaterials science020209 energyMechanical EngineeringNuclear engineeringchemistry.chemical_element02 engineering and technologyBlanket01 natural sciences010305 fluids & plasmasTritium releaseNuclear Energy and EngineeringchemistryNeutron flux0103 physical sciences0202 electrical engineering electronic engineering information engineeringGeneral Materials ScienceNeutronIrradiationBerylliumPebbleHeliumCivil and Structural Engineering
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Germanium Doped CHxMicroshells for LMJ Targets

2011

AbstractAt the CEA Laser “Megajoule” facility, amorphous hydrogenated carbon (a-C:H or CHx) is the nominal ablator used to achieve inertial confinement fusion experiments. These targets are filled with a fusible mixture of deuterium-tritium in order to perform ignition.Since the achievement of ignition greatly depends on the physical properties of the shell, there must be precise control of thicknesses, doping concentration, and roughness. Experimental devices associated with suitable characterizations are described in this paper. The tolerances and yields for each specification are also presented. Some specifications are largely reached; high-frequency surface roughness due to isolated sur…

Nuclear and High Energy PhysicsMaterials science020209 energychemistry.chemical_elementNanotechnologyGermanium02 engineering and technologySurface finish01 natural sciences010305 fluids & plasmas0103 physical sciences0202 electrical engineering electronic engineering information engineeringSurface roughnessGeneral Materials ScienceThin filmInertial confinement fusionCivil and Structural Engineeringbusiness.industryMechanical EngineeringDopingFusible alloyAmorphous solidNuclear Energy and EngineeringchemistryOptoelectronicsbusinessFusion Science and Technology
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A Model to Characterize the D-T Layer of ICF Targets by Backlit Optical Shadowgraphy

2005

A numerical model is presented in order to modelize the bright ring that appears in backlit optical shadowgraphy on a transparent hollow sphere with a solid deuterium-tritium layer inside. This novel model is based on computational calculations applied to the problem of the targets used in inertial confinement fusion. The model takes into account the influences of the optical imaging system (numerical aperture, source divergence, camera resolution, etc.) and the effect of the capsule itself, diameter, thickness, and refractive index, and allows one to analyze the inner surface of a capsule in terms of thickness and roughness.

Nuclear and High Energy PhysicsMaterials scienceComputer simulationbusiness.industry020209 energyMechanical Engineering02 engineering and technologySurface finishBacklightShadowgraphy01 natural sciences010305 fluids & plasmasNumerical apertureOpticsNuclear Energy and EngineeringPhysics::Plasma Physics0103 physical sciences0202 electrical engineering electronic engineering information engineeringGeneral Materials SciencebusinessImage resolutionRefractive indexInertial confinement fusionCivil and Structural EngineeringFusion Science and Technology
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Phenomenological Model for Gold-Copper Electrodeposition: Application to Thick Coatings

2016

Pure gold-copper alloys are known to be difficult to electrodeposit because of a strong variation in composition after a few microns have been deposited. Commissariat al’Energie Atomique (CEA) stud...

Nuclear and High Energy PhysicsMaterials scienceMechanical EngineeringMetallurgychemistry.chemical_element02 engineering and technology010402 general chemistry021001 nanoscience & nanotechnology01 natural sciencesCopper0104 chemical sciencesNuclear Energy and EngineeringchemistryPhenomenological modelGeneral Materials Science0210 nano-technologyCivil and Structural EngineeringFusion Science and Technology
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Hydraulic analysis of EU-DEMO divertor plasma facing components cooling circuit under nominal operating scenarios

2019

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 steady state thermal-hydraulic behaviour of the DEMO divertor cassette cooling circuit, focussing the attention on its Plasma Facing Components (PFCs). 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 code ANSYS-CFX. A realistic model of the PFCs cooling circuit has been analysed, specifically embedding each Plasma Facing Unit (PFU) cooling chann…

Nuclear engineeringCFD analysis; DEMO; Divertor; Plasma facing components; Thermofluid-dynamics7. Clean energy01 natural sciences010305 fluids & plasmasDivertor0103 physical sciencesGeneral Materials ScienceBoundary value problemCFD analysiTotal pressure010306 general physicsDEMOSettore ING-IND/19 - Impianti NucleariPlasma facing componentsCivil and Structural EngineeringThermofluid-dynamicsFinite volume methodSteady stateTurbulenceMechanical EngineeringDivertorPlasma facing componentCoolantVibrationNuclear Energy and EngineeringEnvironmental scienceCFD analysisFusion Engineering and Design
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Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System

2021

Abstract The Water Cooled Lithium Lead Test Blanket System (WCLL TBS) is one of the EU Test Blanket Systems candidate for being installed and operated in ITER. In view of its Conceptual Design Review by F4E and ITER Organization (IO), planned for mid-September 2020, several technical activities have been performed in the areas of WCLL TBS Ancillary Systems design. In this article the outcomes of the conceptual design phase of the four main Ancillary Systems of WCLL TBS, namely the Water Cooling System (WCS), the Coolant Purification System (CPS), the PbLi loop and the Tritium Extraction System (TES), are reported and critically discussed. In particular, for each Ancillary System hereafter a…

Nuclear engineeringCPS; ITER; PbLi loop; TES; WCLL TBS; WCSchemistry.chemical_elementPbLi loopBlanket01 natural sciences010305 fluids & plasmasConceptual designITER0103 physical sciencesWater coolingGeneral Materials Science010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringMechanical EngineeringWater cooledCoolantNuclear Energy and EngineeringchemistryEnvironmental scienceSystems designLithiumCPSWCSTESWCLL TBS
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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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Hydraulic assessment of an upgraded pipework arrangement for the DEMO divertor plasma facing components cooling circuit

2021

Abstract In the context of the Work Package DIVertor (WPDIV) of the EUROfusion action, a research campaign has been carried out by University of Palermo in cooperation with ENEA to assess the thermal-hydraulic performances of the DEMO divertor cooling system, concentrating the attention on its 2019 Plasma Facing Components (PFCs) configuration, relevant to DEMO baseline 2017. The research activity has been performed following a theoretical-numerical technique based on the finite volume method and adopting the well-known ANSYS CFX CFD code. The PFCs cooling circuit thermal-hydraulic performances under nominal steady-state conditions, assessed mainly in terms of coolant total pressure drop, c…

Nuclear engineeringContext (language use)01 natural sciences010305 fluids & plasmaslaw.inventionDivertorlaw0103 physical sciencesWater coolingGeneral Materials ScienceTotal pressure010306 general physicsDEMOPlasma facing componentsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringThermofluid-dynamicsCritical heat fluxMechanical EngineeringDivertorCoolantAxial compressorNuclear Energy and EngineeringEnvironmental scienceInlet manifoldCFD analysis
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Preliminary design of the top cap of DEMO Water-Cooled Lithium Lead breeding blanket segments

2020

Abstract Within the framework of EUROfusion R&D activity, a research campaign has been carried out at the University of Palermo, in close cooperation with ENEA labs, in order to preliminary design the top cap foreseen for the DEMO Water-Cooled Lithium Lead (WCLL) breeding blanket segments. Due to the high heat and pressure loads acting on such component, its design results particularly demanding and a specific multi-physics approach is needed, covering several aspects from thermal-hydraulics to structural assessments. Preliminary detailed CAD model of the cap integrated into the upper region of the WCLL breeding blanket outboard central segment has been set-up, equipped with proper cooling …

Nuclear engineeringchemistry.chemical_elementBlanket7. Clean energy01 natural sciencesTop cap010305 fluids & plasmasLead (geology)Component (UML)0103 physical sciencesGeneral Materials Science010306 general physicsDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringElectronic circuitStructural materialMechanical EngineeringWater cooledCapWCLLNuclear Energy and EngineeringchemistryEnvironmental scienceMulti-physicsLithiumBreeding blanketFusion Engineering and Design
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