Search results for "Anti nuclear"

showing 10 items of 415 documents

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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Linguistic Approach to Support Human Reliability Analysis and Validation Work in Advanced Radiotherapy Technologies

2019

An integrated methodology, that combines Hierarchical Task Analysis (HTA), Cognitive Task Analysis (CTA) and a modified Human Error Assessment and Reduction Technique (HEART), is proposed to identify safety-relevant human actions in innovative and advanced facilities. It is suggested to use in HEART the concept of linguistic expressions for proportion assessment factors. To prove its applicability, a case study is presented. The validation work has related to safety analyses of accidental events that can involve radiological over-exposure of patients during proton therapy treatments carried out by CATANA (Centro di AdroTerapia Applicazioni Nucleari Avanzate) centre, Italy. CATANA is the fir…

Operator human errorAdrotherapyWork (electrical)Computer scienceTask analysisHEARTCentro di AdroTerapia Applicazioni Nucleari AvanzateHuman error assessment and reduction techniqueProton therapySettore ING-IND/19 - Impianti NucleariLinguisticsHierarchical Task AnalysiHuman reliability
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Determination of a pre-heating sequence for the DONES Target Assembly

2021

Abstract Within the activities promoted by the EUROfusion consortium in support of the design and construction of the DEMO Oriented NEutron Source (DONES), a mock-up of its Target Assembly (TA), based on the configuration with a “bayonet” Back-Plate (BP) and available at ENEA Brasimone labs, is being adopted for the execution of experimental activities aiming at the validation of specific aspects of the target design. Despite the “integral”-TA concept is the current reference, experimental tests concerning the TA pre-heating phase are not significantly affected by the TA concept and are still representative even though conducted on the bayonet-TA concept. Indeed, the main objective of the p…

Optimal designTechnologyComputer scienceNuclear engineeringFlow (psychology)Phase (waves)01 natural sciences010305 fluids & plasmas0103 physical sciencesThermalIFMIFGeneral Materials SciencePre-heating010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFEMSteady stateMechanical EngineeringFinite element methodNuclear Energy and EngineeringDuty cycleTarget SystemNeutron sourceDONESddc:600
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Multiphysics Optimization for First Wall Design Enhancement in Water-Cooled Breeding Blankets

2021

Abstract The commercial feasibility of the first fusion power plant generation adopting D-T plasma is strongly dependent upon the self-sustainability in terms of tritium fuelling. Within such a kind of reactor, the component selected to house the tritium breeding reactions is the breeding blanket, which is further assigned to heat power removal and radiation shielding functions. As a consequence of both its role and position, the breeding blanket is heavily exposed to both surface and volumetric heat loads and, hence, its design requires a typical multiphysics approach, from the neutronics to the thermo-mechanics. During last years, a great deal of effort has been put in the optimization of…

OptimizationNuclear and High Energy PhysicsNeutron transportBreeding blanket Complex method Multiphysics Neutronics Optimization ThermomechanicsComputer scienceMaterials Science (miscellaneous)Water cooledMultiphysicsNuclear engineeringMultiphysicsTK9001-9401Structural integrityMaximizationBlanketFusion powerComplex methodThermomechanicsNuclear Energy and EngineeringComponent (UML)NeutronicsNuclear engineering. Atomic powerBreeding blanketSettore ING-IND/19 - Impianti Nucleari
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Optimization of net power density in Reverse Electrodialysis

2019

Abstract Reverse Electrodialysis (RED) extracts electrical energy from the salinity difference between two solutions using selective ion exchange membranes. In RED, conditions yielding a large net power density (NPD) are generally desired, due to the still large cost of the membranes. NPD depends on a large number of physical and geometric parameters. Some of these, for example the inlet concentrations of concentrate and diluate, can be regarded as “scenario” variables, imposed by external constraints (e.g., availability) or chosen by different criteria than NPD maximization. Others, namely the thicknesses HCONC, HDIL and the velocities UCONC, UDIL in the concentrate and diluate channels, c…

OptimizationSettore ING-IND/26 - Teoria Dello Sviluppo Dei Processi ChimiciMathematical optimization020209 energy02 engineering and technologyIndustrial and Manufacturing Engineering020401 chemical engineeringStack (abstract data type)Reversed electrodialysisReverse electrodialysi0202 electrical engineering electronic engineering information engineering0204 chemical engineeringElectrical and Electronic EngineeringSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringPower densityMathematicsGradient ascentOptimization algorithmMechanical EngineeringElectric potential energySalinity gradientBuilding and ConstructionMaximizationNet (mathematics)PollutionNet power densityGeneral EnergyIon-exchange membranesEnergy
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Effetto della distribuzione della densità di potenza sulle analisi della composizione finale del combustibile di un PWR effettuate con Origen2

2003

Previsione, mediante codice di calcolo, della composizione finale del combustibile utilizzato in un reattore tipo PWR, in relazione al suo tempo di funzionamento ed alla densità di potenza impiegata.

Origen2PWR AttinidiSettore ING-IND/19 - Impianti Nucleari
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