Search results for "Anti nuclear"

showing 10 items of 415 documents

Analysis of the thermomechanical behavior of the IFMIF bayonet target assembly under design loading scenarios

2015

In the framework of the IFMIF Engineering Validation and Engineering Design Activities (IFMIF/EVEDA) phase, ENEA is responsible for the design of the European concept of the IFMIF lithium target system which foresees the possibility to periodically replace only the most irradiated and thus critical component (i.e., the backplate) while continuing to operate the rest of the target for a longer period (the so-called bayonet backplate concept). In this work, the results of the steady state thermomechanical analysis of the IFMIF bayonet target assembly under two different design loading scenarios (a "hot" scenario and a "cold" scenario) are briefly reported highlighting the relevant indications…

Steady stateEngineering designComputer scienceMechanical EngineeringNuclear engineeringStructural integrityIFMIF Target assembly Bayonet backplate Engineering design ThermomechanicsThermomechanicStress (mechanics)ThermomechanicsHigh fluxNuclear Energy and EngineeringLinearizationTarget assemblyComponent (UML)Thermomechanics;Bayonet backplate;Engineering design;Target assembly;IFMIFIFMIFGeneral Materials ScienceEngineering design processBayonet backplateMiddle planeSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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On the thermomechanical behavior of the European target assembly design of IFMIF-EVEDA lithium test loop under start-up transient scenarios

2013

Uncoupled thermomechanical transient analyses have been carried out to investigate the behavior of IFMIF-EVEDA lithium test loop bayonet backplate target assembly under two selected start-up transient operational scenarios. The first transient scenario considered foresees that the target assembly, starting from the initial uniform temperature of 50 C, is heated up uniquely by convective heat transfer with lithium, flowing from inlet to outlet nozzle at its reference nominal temperature and pressure, until its nominal steady state thermal field distribution is reached. The second transient scenario foresees, more realistically, that the target assembly, starting from the uniform temperature …

Steady stateMaterials scienceConvective heat transferMechanical EngineeringNozzleFlow (psychology)chemistry.chemical_elementMechanicsThermomechanicsIFMIF-EVEDA lithium test loop Target assembly Thermomechanics Start-up transientTarget assembly;Start-up transient;IFMIF-EVEDA lithium test loop;ThermomechanicsNuclear Energy and EngineeringHeat fluxchemistryIFMIF-EVEDA lithium test loopTarget assemblyThermalStart-up transientGeneral Materials ScienceLithiumTransient (oscillation)Settore ING-IND/19 - Impianti NucleariCivil and Structural Engineering
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Study of the thermo-mechanical performances of the IFMIF-EVEDA Lithium Test Loop target assembly

2012

Abstract Within the framework of the IFMIF R&D program and in close cooperation with ENEA-Brasimone, at the Department of Energy of the University of Palermo a research campaign has been launched to investigate the thermo-mechanical behavior of the target assembly under both steady state and start-up transient conditions. A theoretical approach based on the finite element method (FEM) has been followed and a well-known commercial code has been adopted. A realistic 3D FEM model of the target assembly has been set-up and optimized by running a mesh independency analysis. A proper set of loads and boundary conditions, mainly concerned with radiation heat transfer between the target assembly ex…

Steady stateMaterials scienceIFMIF Target assembly Thermo-mechanicsMechanical EngineeringNuclear engineeringLithium testFinite element methodLoop (topology)Hydrostatic testNuclear Energy and EngineeringHeat transferGeneral Materials ScienceTransient (oscillation)Boundary value problemSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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Optimization of the breeder zone cooling tubes of the DEMO Water-Cooled Lithium Lead breeding blanket

2016

Abstract The determination of an optimal configuration for the breeder zone (BZ) cooling tubes is one of the most important issues in the DEMO Water-Cooled Lithium Lead (WCLL) breeding blanket R&D activities, since BZ cooling tubes spatial distribution should ensure an efficient heat power removal from the breeder, avoiding hotspots occurrence in the thermal field. Within the framework of R&D activities supported by the HORIZON 2020 EUROfusion Consortium action on the DEMO WCLL breeding blanket design, a campaign of parametric analyses has been launched at the Department of Energy, Information Engineering and Mathematical Models of the University of Palermo (DEIM), in close cooperation with…

Steady stateMathematical modelDEMO reactor WCLL breeding blanket Breeder zone cooling tubesMechanical EngineeringNuclear engineeringchemistry.chemical_elementBlanket7. Clean energy01 natural sciencesFinite element method010305 fluids & plasmasBreeder (animal)Nuclear Energy and Engineeringchemistry0103 physical sciencesThermalEnvironmental scienceGeneral Materials ScienceLithium010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringParametric statisticsFusion Engineering and Design
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Numerical assessment of the thermomechanical behaviour of the DEMO Water-Cooled Lithium Lead inboard blanket equatorial module

2018

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 assess the thermo-mechanical performances of the DEMO Water-Cooled Lithium Lead (WCLL) inboard blanket equatorial module, whether properly integrated within its whole inboard segment. In particular, a detailed 3D model of this segment, including all the other modules, the back-supporting structure and the attachment system, has been considered in order to realistically simulate the boundary conditions affecting the equatorial module behaviour. The study has been focused on the investigation of the module thermo-mech…

Structural materialComputer scienceMechanical EngineeringNuclear engineeringThermo-mechanicBlanket01 natural sciencesFinite element method010305 fluids & plasmasStress (mechanics)WCLL blanketNuclear Energy and EngineeringCabin pressurizationLinearization0103 physical sciencesGeneral Materials ScienceMaterials Science (all)Boundary value problem010306 general physicsDEMOFEM analysiLoss-of-coolant accidentSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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Neutronic and photonic analysis of the water-cooled Pb17Li test blanket module for ITER-FEAT

2002

Abstract Within the European Fusion Technology Program, the Water-Cooled Lithium Lead (WCLL) DEMO breeding blanket line was selected in 1995 as one of the two EU lines to be developed in the next decade, in particular with the aim of manufacturing a Test Blanket Module (TBM) to be implemented in ITER. This specific goal has been maintained also in ITER-FEAT program even if the general design parameters of the TBMs have reported some changes. This paper is focused on the investigation of the WCLL-TBM nuclear response in ITER-FEAT through detailed 3D-Monte Carlo neutronic and photonic analyses. A 3D heterogeneous model of the most recent design of the WCLL-TBM has been set-up simulating reali…

Structural materialMaterials sciencebusiness.industryNeutronicMechanical EngineeringWater cooledPower depositionNuclear engineeringPhotonicchemistry.chemical_elementFusion powerBlanketMonte Carlo methodNuclear physicsNuclear Energy and EngineeringchemistryNeutron sourceGeneral Materials ScienceLithiumBreeding blanketPhotonicsbusinessSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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On the nuclear response of the water-cooled Pb-17Li test blanket module for ITER-FEAT

2003

Abstract Within the European Fusion Technology Programme, the Water-Cooled Lithium Lead (WCLL) DEMO breeding blanket line was selected in 1995 as one of the two EU lines to be developed in the next decades, in particular with the aim of manufacturing a Test Blanket Module (TBM) to be tested in ITER-FEAT. The present paper is focused on the study of the WCLL-TBM nuclear response in ITER-FEAT, being specifically oriented to the investigation of the local effects due to the typical C-shaped tubes of the breeder zone, since they could play a pivotal role in the module-relevant thermo–mechanical design. A 3D heterogeneous model of the WCLL-TBM, realistically simulating its new lay out and taking…

Structural materialMechanical EngineeringWater cooledNuclear engineeringchemistry.chemical_elementBlanketFusion powerCluster (spacecraft)ITER-FEATNuclear physicsBreeder (animal)Nuclear Energy and EngineeringchemistryEnvironmental scienceNeutron sourceGeneral Materials ScienceLithiumBlanket modulePb/17LiSettore ING-IND/19 - Impianti NucleariCivil and Structural Engineering
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Thermomechanical analysis supporting the preliminary engineering design of DONES target assembly

2018

Abstract The design of the Demo Oriented NEutron Source (DONES) is the main objective of the Work Package Early Neutron Source (WPENS) of EUROfusion Power Plant Physics and Technology (PPPT) programme. DONES is an IFMIF-based neutron source with the goal of testing and qualifying candidate materials to be used in DEMO and future fusion power plants. In the framework of these activities, a research campaign has been carried out at the University of Palermo, in close cooperation with ENEA labs, in order to assess the thermomechanical performances of the DONES target system, endowed with an integrated Target Assembly (TA) when it undergoes the thermomechanical loads typical of its nominal oper…

Structural materialPower stationMechanical EngineeringNuclear engineeringFusion power7. Clean energy01 natural sciencesThermomechanicFinite element method010305 fluids & plasmasNuclear Energy and EngineeringTarget assemblyLinearization0103 physical sciencesIFMIFNeutron sourceDONESGeneral Materials ScienceMaterials Science (all)010306 general physicsEngineering design processFEM analysiSettore ING-IND/19 - Impianti NucleariBeam (structure)Civil and Structural EngineeringFusion Engineering and Design
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Structural analysis of the back supporting structure of the DEMO WCLL outboard blanket

2017

Abstract Within the framework of EUROfusion R&D activities an intense research campaign has been carried out at the University of Palermo, in close cooperation with ENEA Brasimone, in order to investigate the thermo-mechanical performances of the outboard segment Back-Supporting Structure (BSS) of the DEMO Water-Cooled Lithium Lead breeding blanket (WCLL). In particular, the configuration of the outboard segment BSS, purposely set-up by the WCLL project team during 2015 according to the blanket “multi-module system” concept, has been taken into account in order to study its steady state thermo-mechanical behaviour, paying attention to the simulation of both modules-BSS and BSS-vacuum vessel…

Structure (mathematical logic)business.industryComputer scienceMechanical EngineeringDEMO reactor WCLL blanket BSSDEMO reactorStructural engineeringBlanket01 natural sciencesProject teamFinite element method010305 fluids & plasmasWCLL blanketGeometric designNuclear Energy and EngineeringLinearization0103 physical sciencesSafety criteriaGeneral Materials Science010306 general physicsbusinessBSSSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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Hydraulic characterization of the full scale divertor cassette prototype

2011

In the frame of the activities related to ITER divertor R&D, ENEA C.R. Brasimone was in charge by Fusion For Energy (F4E) to perform the assembly, the hydraulic tests and the theoretical simulation of the hydraulic behavior of the full scale divertor cassette prototype. The objective of these activities was aimed at the investigation of the thermal-hydraulic behavior of the full-scale divertor cassette both under steady state condition and during draining and drying operational transient. In particular, the steady state tests were focused on finally check whether the hydraulic design of the divertor components is able to ensure a uniform and proper cooling for the plasma facing components, …

System codeNuclear Energy and EngineeringITER Divertor Draining and dryingMechanical EngineeringNuclear engineeringDivertorFull scaleEnvironmental scienceGeneral Materials ScienceTransient (oscillation)Settore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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