Search results for "Blanket"

showing 10 items of 141 documents

Design and manufacturing feasibility of ITER TBM Frame and Dummy TBMs

2016

Abstract The operation and test of mock-ups of tritium breeding blankets relevant for a future commercial reactor is one of the goals of the ITER machine. To accomplish this goal, mock-ups of breeding blankets, called Test Blanket Modules (TBMs), are installed in three ITER equatorial ports. Each TBM and the associated shield form a TBM-set that is mechanically attached to a steel frame called TBM Frame. A Frame and two TBM-Sets form a TBM Port Plug (TBM PP). The ITER Organization is responsible for the design and manufacture of the TBM Frames and of the Dummy TBMs that could replace the TBM-sets in case they were not available. This paper describes the recent results of the design supporti…

Light nucleusDesign stageComputer scienceMechanical EngineeringNuclear engineeringFrame (networking)Iron alloysIter tokamakBlanket01 natural sciences010305 fluids & plasmasNuclear Energy and EngineeringSteel frameShieldITER Test blanket module (TBM) TBM port plug (TBM PP) Frame Dummy TBM0103 physical sciencesGeneral Materials Science010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural Engineering
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Characterization and thermomechanical assessment of a SiC-sandwich material for Flow Channel Inserts in DCLL blankets

2019

Abstract Flow Channel Inserts (FCIs) are key elements in the high-temperature Dual Coolant Lead Lithium (DCLL) blanket, since they insulate electrically the flowing PbLi to avoid MHD effects and protect the steel structure from the hot liquid metal. SiC-based materials are main candidates for high-temperature FCIs, being a dense-porous SiC-based sandwich material an attractive option. The present work is focused on the development of such a SiC-based material. On the one hand, in order to assess the suitability of the concept for FCIs, the main results of a stress analysis, MHD and heat transfer simulations are summarized. On the other hand, the experimental production of the SiC-based mate…

Liquid metalMaterials scienceMechanical EngineeringBlanketengineering.material7. Clean energy01 natural sciences010305 fluids & plasmasCoolantCorrosionStress (mechanics)Nuclear Energy and EngineeringCoatingFlexural strength0103 physical sciencesengineeringGeneral Materials ScienceComposite material010306 general physicsPorosityCivil and Structural EngineeringFusion Engineering and Design
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Thermal-hydraulic and thermo-mechanical simulations of Water-Heavy Liquid Metal interactions towards the DEMO WCLL breeding blanket design

2019

Abstract The Water-Cooled Lithium Lead breeding blanket concept foresees the eutectic lithium-lead (Pb-15.7Li) alloy being cooled by pressurized sub-cooled water (temperature 295–328 °C; pressure 15.5 MPa) flowing in double wall tubes. Therefore, the interaction between the Pb-15.7Li and water (e.g. tube rupture) represents one of the main safety concerns for the design and safety analysis. Available LIFUS5/Mod2 experimental data are employed to assess the performances of thermal-hydraulic and thermo-mechanic codes. Thermal-hydraulic simulations, by SIMMER-III code, are focused on the prediction of the thermodynamic interaction among the fluids. ABAQUS Finite Element code, used for the desi…

Liquid metalMaterials scienceNuclear engineeringchemistry.chemical_elementBlanket01 natural sciences010305 fluids & plasmasThermal hydraulics0103 physical sciencesGeneral Materials ScienceTube (fluid conveyance)010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringEutectic systemMechanical EngineeringStress–strain curveWater-Liquid metal interactionExperimental dataBreeding blanket; LIFUS5; Water-Liquid metal interactionsWater-Liquid metal interactionsNuclear Energy and EngineeringchemistryLithiumBreeding blanketLIFUS5
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Assessment of the Thermo-mechanical Performances of a DEMO Water-Cooled Liquid Metal Blanket Module

2015

Within the framework of DEMO R&D activities, a research cooperation has been launched between ENEA-Brasimone, CEA-Saclay and the University of Palermo to investigate the thermo-mechanical behaviour of the outboard equatorial module of the DEMO1 Water-Cooled Lithium Lead (WCLL) blanket, both under normal operation and over-pressurization steady state scenarios. 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 three-dimensional FEM models of the WCLL blanket module have been set-up to be used for normal operation and over-pressurization a…

Liquid metalNuclear and High Energy PhysicsMaterials science[PHYS.NUCL]Physics [physics]/Nuclear Theory [nucl-th]Nuclear engineeringDEMO reactorBlanket[PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]01 natural sciences7. Clean energyThermo-mechanics;DEMO reactor;WCLL blanket010305 fluids & plasmasBreeder (animal)0103 physical sciencesThermal010306 general physicsSettore ING-IND/19 - Impianti NucleariSteady stateToroidThermo-mechanicsThermo-mechanic6. Clean waterFinite element methodCoolantWCLL blanketNuclear Energy and Engineering
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Progress in the benchmark exercise for analyzing the lithiate breeder pebble bed thermo-mechanical behaviour

2006

The Helium Cooled Pebble Bed (HCPB) Blanket is one of the reference concepts for the European Breeding Blanket Programme for DEMO. In the reference blanket module, alternate layers of lithiated ceramics and beryllium pebbles act, respectively, as tritium breeder and neutron multiplier. The thermo-mechanical behaviour of both the pebble beds and their performances in reactor relevant conditions are also dependent on the pebble size and cell geometries (bed thickness, pebble packing factor, bed thermal conductivity). Therefore, in the EU Fusion Technology Programme, several out-of-pile experimental test campaigns have been performed to determine these behaviours. Theoretical calculations have…

Lithiated ceramicMechanical EngineeringNuclear engineeringchemistry.chemical_elementBlanketFusion powerBreederAtomic packing factorCalculation methodsThermo-mechanical behaviourNuclear Energy and EngineeringchemistryThermal mechanicalGeneral Materials ScienceBerylliumPebbleSettore ING-IND/19 - Impianti NucleariThermo mechanicalCivil and Structural EngineeringFusion Engineering and Design
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Accelerating Causal Inference and Feature Selection Methods through G-Test Computation Reuse

2021

This article presents a novel and remarkably efficient method of computing the statistical G-test made possible by exploiting a connection with the fundamental elements of information theory: by writing the G statistic as a sum of joint entropy terms, its computation is decomposed into easily reusable partial results with no change in the resulting value. This method greatly improves the efficiency of applications that perform a series of G-tests on permutations of the same features, such as feature selection and causal inference applications because this decomposition allows for an intensive reuse of these partial results. The efficiency of this method is demonstrated by implementing it as…

Markov blanketMarkov blanketComputer sciencecomputation reuseConditional mutual informationComputationSciencePhysicsQC1-999QGeneral Physics and AstronomyContext (language use)Feature selectionInformation theoryAstrophysicsJoint entropyArticleG-testQB460-466feature selectionCausal inferencecausal inferenceAlgorithminformation theoryEntropy
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Tritium release from breeding blanket materials in high magnetic field

2007

Abstract Under the operating conditions of a fusion reactor, the blanket materials: ceramic and Be pebbles will be at a high temperature (up to 1123 K), under action of intense radiation (up to 10 19  n m −2  s −1 ) and magnetic field (MF) up to 7–10 T. In order to introduce action of radiation and MF in post-irradiation investigations of the tritium release from the blanket materials, a special rig for thermo-annealing of pre-irradiated samples at a high temperature up to 1120 K under irradiation with fast electrons of 5 MeV and dose rate 14 MGy/h in MF up to 1.7 T was used for this study. A delay of the tritium release in MF of 2.4 T at thermo-annealing of the lithium orthosilicate Li 4 S…

Materials scienceAnnealing (metallurgy)Mechanical EngineeringRadiochemistrychemistry.chemical_elementFusion powerBlanketchemistry.chemical_compoundNuclear Energy and Engineeringchemistryvisual_artvisual_art.visual_art_mediumGeneral Materials ScienceTritiumCeramicIrradiationOrthosilicateBerylliumCivil and Structural EngineeringFusion Engineering and Design
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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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