Search results for " blanket"

showing 10 items of 86 documents

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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Modelling of the thermal mechanical behaviour of a single size beryllium pebble bed

2001

The Helium Cooled Pebble Bed (HCPB) Blanket for fusion power reactors and the ITER breeding blanket are based on the use of pebble beds of lithium ceramics as breeder and beryllium as neutron multiplier. Experimental activities were performed at Forschungszentrum Karlsruhe concerning the measurement of pebble bed heat transfer parameters. At the Department of Nuclear Engineering of the University of Palermo, the experimental results have been reproduced by means of the ABAQUS finite element code. Moreover, a thermal-mechanical theoretical model has been developed for single size beryllium pebble beds. In the paper the results from the numerical and theoretical analyses and the comparison wi…

Materials sciencePebble-bed reactorMechanical EngineeringNuclear engineeringchemistry.chemical_elementNuclear reactorFusion powerBlanketThermo-mechanical tests and modelslaw.inventionNuclear physicsNuclear Energy and EngineeringchemistrylawHeat transferGeneral Materials ScienceNeutronBreeding blanketBerylliumPebbleSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringBeryllium pebble bed
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Thermo-mechanical analyses and ways of optimization of the helium cooled DEMO First Wall under RCC-MRx rules

2017

Abstract The EUROfusion Consortium develops a design of a fusion power demonstrator plant (DEMO) in the framework of the European “Horizon 2020” innovation and research program. One of the key components in the fusion reactor is the Breeding Blanket (BB) surrounding the plasma, ensuring tritium self-sufficiency, heat removal for conversion into electricity, and neutron shielding. Among the 4 candidates for the DEMO BB, 2 of them use helium as coolant (HCPB, HCLL), and another one (DCLL) uses helium to cool down the First Wall (FW) only. Due to uncertainties regarding the plasma Heat Flux (HF) load the DEMO BB integrated FW will have to cope with, a set of sensitive thermal and stress analys…

Materials scienceRCC-MRxNuclear engineeringchemistry.chemical_elementBlanket01 natural sciences7. Clean energy010305 fluids & plasmasStress (mechanics)[SPI]Engineering Sciences [physics]Materials Science(all)0103 physical sciencesGeneral Materials ScienceCast3M010306 general physicsDEMOHeliumSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringSteady stateBreeding BlanketMechanical EngineeringThermo-mechanicFusion powerCoolantFirst WallchemistryCreepHeat fluxNuclear Energy and EngineeringHCLLDEMO; Breeding; Blanket; HCLL; RCC-MRx; Thermo-mechanics; Cast3M; First WallMaterials Science (all)
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SiC-based sandwich material for Flow Channel Inserts in DCLL blankets: Manufacturing, characterization, corrosion tests

2017

This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014–2018 under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission.

Materials scienceSintering02 engineering and technologyengineering.materialBlanket7. Clean energy01 natural sciences010305 fluids & plasmasCorrosionFlexural strengthThermal conductivityFlexural strengthCoatingThermal insulationCorrosion by PbLi0103 physical sciences:NATURAL SCIENCES:Physics [Research Subject Categories]General Materials ScienceComposite materialCivil and Structural Engineeringbusiness.industryMechanical EngineeringFCI021001 nanoscience & nanotechnologyMicrostructurePorous SiCCVD-SiC coatingDCLL blanketNuclear Energy and EngineeringThermal conductivityengineering0210 nano-technologybusinessFusion Engineering and Design
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Multi-Module vs. Single-Module concept: Comparison of thermomechanical performances for the DEMO Water-Cooled Lithium Lead breeding blanket

2018

Abstract Within the framework of EUROfusion R&D activity an intense research campaign has been performed at the University of Palermo, in close cooperation with ENEA labs and KIT, in order to compare the thermomechanical performances of the Back Supporting Structure (BSS) of Multi-Module and Single-Module concepts of DEMO Water-Cooled Lithium Lead breeding blanket (WCLL). To this purpose, detailed 3D models of the DEMO WCLL right inboard and central outboard segments, including detailed BSS and simplified First Wall and structures according to the two concepts, have been set-up. The study has been performed considering the Normal Operation and Central Major Disruption steady state loading s…

Materials sciencechemistry.chemical_elementBlanket01 natural sciencesThermomechanic010305 fluids & plasmasStress (mechanics)Linearization0103 physical sciencesForensic engineeringGeneral Materials Science010306 general physicsDEMOFEM analysiSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringSteady stateStructural materialbusiness.industryMechanical EngineeringWater cooledStructural engineeringMMSFinite element methodWCLLNuclear Energy and EngineeringchemistrySMSLithiumBreeding blanketMaterials Science (all)businessFusion Engineering and Design
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A multi-physics integrated approach to breeding blanket modelling and design

2019

Abstract Often, for the design of a component, several kinds of analyses are needed. Even more frequently, the different fields of study, to be taken into account for the design verification, have to be examined minutely until the final results are satisfying. Furthermore, when geometry modifications are required, for instance to fulfill the component functions, the analyses cycle has to be restarted and an iterative process has to be carried out. This procedure may be time-consuming and herald of errors, in particular if it is demanded to the human activity. Therefore, it is more convenient for the scientific community to adopt a numerical tool that can combine various computational codes.…

Multi-physicCommercial softwareNeutron transportIterative and incremental developmentHCPBMechanical EngineeringBase (geometry)Blanket7. Clean energy01 natural sciencesWCLL010305 fluids & plasmasCouplingLead (geology)Nuclear Energy and EngineeringCoupling (computer programming)Component (UML)0103 physical sciencesSystems engineeringGeneral Materials ScienceBreeding blanket010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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Thermal-hydraulic and thermal-structural analyses report of DEMO Helium-Cooled Pebble Bed blanket

2012

NUCLEAR FUSION HCPB BLANKETSettore ING-IND/19 - Impianti Nucleari
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A Thermo-Mechanical Constitutive Model of the Lithium Orthosilicate and Beryllium Pebble Beds. An Application on the Thermo-Mechanical Study of the S…

2000

NUCLEAR FUSION PEBBLE BEDS BREEDING BLANKET SMARTS MOCK-UP
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Thermal tests of ceramic breeder pebble beds for the Helium Cooled (HCPB) DEMO blanket

2002

NUCLEAR FUSION PEBBLE BEDS HCPB BLANKET
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