Search results for "Anti nuclear"

showing 10 items of 415 documents

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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Analysis of the thermo-mechanical behaviour of the DEMO Water-Cooled Lithium Lead breeding blanket module under normal operation steady state conditi…

2015

Within the framework of DEMO R&D activities, a research cooperation has been launched between ENEA, the University of Palermo and CEA to investigate the thermo-mechanical behaviour of the outboard equatorial module of the DEMO1 Water-Cooled Lithium Lead (WCLL) blanket under normal operation steady state scenario. 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 3D FEM models (Model 1 and Model 2), reproducing respectively the central and the lateral poloidal-radial slices of the WCLL blanket module, have been set up. A particular attent…

Materials scienceDEMO reactor WCLL blanket Thermo-mechanicsaWater flowNuclear engineeringchemistry.chemical_elementDEMO reactorBlanket01 natural sciences010305 fluids & plasmas[SPI]Engineering Sciences [physics]Breeder (animal)0103 physical sciencesGeneral Materials Science010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringWCLL blanket;Thermo-mechanics;DEMO reactorSteady stateThermo-mechanicsMechanical EngineeringWater cooledThermo-mechanicFinite element methodWCLL blanketNuclear Energy and EngineeringchemistryLithiumThermo mechanicalFusion Engineering and Design
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On the thermal and thermomechanical assessment of the “Optimized Conservative” helium-cooled lithium lead breeding blanket concept for DEMO

2018

Abstract Within the framework of EUROfusion R&D activities a research campaign has been performed at CEA-Saclay, in close collaboration with the University of Palermo, in order to investigate thermal and thermomechanical performances of the “Optimized Conservative” concept of DEMO Helium-Cooled Lithium Lead breeding blanket (HCLL). Attention has been paid to the HCLL outboard equatorial module (OEM) when subjected to the steady state nominal loading scenario. To this purpose three simplified 3D models, characterized by an increasing level of detail, have been set-up taking into account, firstly, a single radial-toroidal slice, then a basic module geometric unity composed by two adjacent sli…

Materials scienceDiscretizationNuclear engineeringFEM analysisBlanket01 natural sciencesThermomechanic010305 fluids & plasmasStress (mechanics)Thermomechanics[SPI]Engineering Sciences [physics]Linearization0103 physical sciencesThermalGeneral Materials Science010306 general physicsFEM analysiDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringMechanical EngineeringSecondary stressFinite element methodNuclear Energy and EngineeringHCLLMaterials Science (all)Breeding blanketReduction (mathematics)
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Modeling of ITER TF cooling system through 2D thermal analyses and enthalpy balance

2017

Abstract The winding pack of the ITER Toroidal Field (TF) coils is composed of 134 turns of Nb3Sn Cable in Conduit Conductor (CICCs) wound in 7 double pancakes and cooled by supercritical helium (He) at cryogenic temperature. The cooling of the Stainless Steel (SS) case supporting the winding pack is guaranteed by He circulation in 74 parallel channels. A 2D approach to compute the temperature distribution in the ITER TF winding pack is here proposed. The TF is divided in 32 poloidal segments, for each segment the corresponding 2D model is built and a thermal analysis is performed applying the corresponding nuclear heating computed with MCNP code considering the latest design updates, such …

Materials scienceMechanical EngineeringBulk temperatureTF winding packchemistry.chemical_elementMechanicsHeat transfer coefficientBlanket01 natural sciencesNusselt number010305 fluids & plasmasThermal conductivitychemistryNuclear Energy and EngineeringElectromagnetic coil0103 physical sciencesNuclear HeatingWater coolingGeneral Materials ScienceMaterials Science (all)010306 general physicsFE thermal analysiHeliumSettore ING-IND/19 - Impianti NucleariCivil and Structural Engineering
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On the thermal-hydraulic performances of the DEMO divertor cassette body cooling circuit equipped with a liner

2020

Abstract In 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 performances of the DEMO divertor cassette cooling system. The research activity has been focussed onto the most recent design of the Cassette Body (CB) cooling circuit, consistent with the DEMO baseline 2017 and equipped with a liner, whose main function is to protect the underlying vacuum pump CB opening from plasma radiation. The research campaign has been carried out following a theoretical-computational approach based on the finite vo…

Materials scienceNuclear engineeringComputational fluid dynamics01 natural sciences010305 fluids & plasmaslaw.inventionThermal hydraulicsDivertorlaw0103 physical sciencesWater coolingGeneral Materials ScienceTotal pressure010306 general physicsDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFinite volume methodThermofluid-dynamicsCassette bodybusiness.industryMechanical EngineeringDivertorCoolantNuclear Energy and EngineeringVacuum pumpbusinessCFD analysisFusion Engineering and Design
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Thermal-hydraulic study of the DEMO divertor cassette body cooling circuit equipped with a liner and two reflector plates

2021

Abstract In 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 performances of the DEMO divertor cassette cooling system. The research activity has been focussed onto the most recent design of the Cassette Body (CB) cooling circuit, consistent with the DEMO baseline 2017 and equipped with a liner and two Reflector Plates (RPs), whose main functions are to protect the underlying vacuum pump hole from the radiation arising from plasma and shield the PFCs inlet distributors, respectively. The research ca…

Materials scienceNuclear engineeringComputational fluid dynamics7. Clean energy01 natural sciences010305 fluids & plasmaslaw.inventionThermal hydraulicsDivertorlawShield0103 physical sciencesWater coolingGeneral Materials Science010306 general physicsDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringThermofluid-dynamicsCassette bodybusiness.industryMechanical EngineeringDivertorCassette body CFD analysis DEMO Divertor Thermofluid-dynamicsCoolantNuclear Energy and EngineeringFlow velocityVacuum pumpbusinessCFD analysis
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Thermal optimization of the Helium-Cooled Lithium Lead breeding zone layout design regarding TBR enhancement

2017

Abstract Within the framework of EUROfusion R&D activities, CEA-Saclay has carried out an investigation of the thermal and mechanical performances of alternative designs intended to enhance the Tritium Breeding Ratio (TBR) of the Helium-Cooled Lithium Lead (HCLL) Breeding Blanket (BB) for DEMO. Neutronic calculations performed on the 2014 DEMO HCLL baseline predicted a value of TBR equal to 1.07, lower than the required value of 1.1, necessary to ensure the tritium self-sufficiency of the breeding blanket taking into account uncertainties. In order to reach the TBR target, the strategy of the steel amount reduction inside the HCLL module breeding zone (BZ) has been followed by suppressing s…

Materials scienceNuclear engineeringFinite elementschemistry.chemical_elementDEMO HCLL Breeding blanket Thermo-mechanics Finite elements Cast3MBlanketcomputer.software_genre01 natural sciences7. Clean energy010305 fluids & plasmas[SPI]Engineering Sciences [physics]Materials Science(all)0103 physical sciencesThermalGeneral Materials ScienceCast3M010306 general physicsDEMOHeliumSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringThermo-mechanicsPage layoutMechanical EngineeringFinite element methodStiffeningchemistryNuclear Energy and EngineeringHCLLBreeding blanketReduction (mathematics)Loss-of-coolant accidentcomputerFusion Engineering and Design
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On the effect of stiffening plates configuration on the DEMO Water Cooled Lithium Lead Breeding Blanket module thermo-mechanical behaviour

2019

Abstract Within the framework of the pre-conceptual design of the EU-DEMO Breeding Blanket (BB) supported by EUROfusion action, results of the research activities carried out in the last years have highlighted that changes in the proposed Water Cooled Lithium Lead (WCLL) BB design have to be considered, especially as to the liquid breeder circulation path within the BB module. Therefore, in view of the definition of a final WCLL BB module layout, a parametric campaign of numerical analyses has been carried out at the University of Palermo in order to assess the impact of different SPs configurations on the module thermo-mechanical performances. To this purpose, attention has been focussed o…

Materials scienceNuclear engineeringFlow (psychology)chemistry.chemical_elementFEM analysisBlanket01 natural sciences010305 fluids & plasmasBreeder (animal)0103 physical sciencesGeneral Materials Science010306 general physicsDEMOFEM analysiSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringParametric statisticsThermo-mechanicsMechanical EngineeringThermo-mechanicDEMO; FEM analysis; Thermo-mechanics; WCLL blanketFinite element methodStiffeningWCLL blanketNuclear Energy and EngineeringchemistryLithiumLoss-of-coolant accident
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Start-up and shutdown thermomechanical transient analyses of the IFMIF European lithium target system

2014

In the framework of the current 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 (bayonet backplate concept). With the objective of evaluating the performances of the system in terms of temperature, stress and displacement fields evolution during start-up and shutdown phases, an uncoupled thermomechanical transient analysis has been performed in close collaboration w…

Materials scienceNuclear engineeringIFMIF Target assembly Bayonet backplate Thermomechanics Start-up ShutdownStart-upShutdown7. Clean energy01 natural sciencesThermomechanic010305 fluids & plasmasStress (mechanics)ThermomechanicsTarget assembly0103 physical sciencesThermalIFMIFGeneral Materials ScienceNeutron010306 general physicsBayonet backplateSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringMechanical EngineeringNuclear dataFinite element methodIFMIF;Bayonet backplate;Thermomechanics;Start-up;Shutdown;Target assemblyNuclear Energy and EngineeringSystems designTransient (oscillation)Engineering design process
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Safety analysis of the DONES primary heat removal system

2020

Abstract The development of a neutron source able to reproduce the irradiation conditions typical of a nuclear fusion reactor, in order to test candidate structural materials, is the main goal of the Work Package Early Neutron Source (WPENS) of the EUROfusion action. This source, named Demo Oriented NEutron Source (DONES), is a facility where neutrons are produced by means of D-Li interactions. More in detail, a beam of 125 mA deuterium ions at the energy of 40 MeV strikes a lithium jet flowing in a purposely shaped channel in order to obtain an intense and stable neutron flux for the irradiation of material samples. In the framework of these activities, safety analyses are a key aspect in …

Materials scienceNuclear engineeringLithium loopchemistry.chemical_element7. Clean energy01 natural sciences010305 fluids & plasmasMELCORNeutron flux0103 physical sciencesMELCORRelap5-3DGeneral Materials ScienceNeutron010306 general physicsSafety analysisSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringMechanical EngineeringFusion powerNuclear Energy and EngineeringchemistryPHRSNeutron sourceLithiumDONESFailure mode and effects analysisBeam (structure)
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