Search results for "breeding blanket"

showing 10 items of 43 documents

On the effects of the Double-Walled Tubes lay-out on the DEMO WCLL breeding blanket module thermal behavior

2019

Abstract The EU-DEMO Water-Cooled Lithium Lead Breeding Blanket (WCLL BB) concept foresees liquid Pb-15.7Li eutectic alloy as breeder and neutron multiplier, whereas pressurized subcooled water as coolant, with operative conditions typical of the PWR fission reactors (temperature in the range of 295–328 °C and pressure of 15.5 MPa). The cooling down of the BB is guaranteed by means of two separated cooling circuits: the one consisted in square channels housed within the complex of Side Walls and First Wall, and the one composed of a set of Double-Walled Tubes (DWTs) submerged in the Breeding Zone (BZ) and deputed to remove heat power therein generated. A parametric thermal study has been ca…

FEMBreeding BlanketMaterials scienceMechanical EngineeringNuclear engineeringBlanket7. Clean energy01 natural sciencesFinite element methodWCLL010305 fluids & plasmasCoolantSubcoolingNuclear Energy and Engineering0103 physical sciencesThermalGeneral Materials ScienceDWT010306 general physicsDEMOSettore ING-IND/19 - Impianti NucleariCooling downCivil and Structural EngineeringElectronic circuitParametric statisticsFusion Engineering and Design
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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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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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Identification of blanket design points using an integrated multi-physics approach

2017

Abstract The breeding blanket (BB) is one of the key components for a fusion reactor. It is expected to sustain and remove considerable heat loads due to the heat flux coming from the plasma and the nuclear power deposited by the fusion neutrons. In the design of the BB, the engineering requirements of nuclear, material and safety kind are involved. In the European DEMO project, several efforts are dedicated to the development of an integrated simulation-design tool able to perform a multi-physics analysis, allowing the characterisation of BB design points which are consistent from the neutronic, thermal-hydraulic and thermo-mechanical point of view. Furthermore, at Karlsruhe Institute of T…

TechnologyNuclear engineeringDEMO reactorBlanket7. Clean energy01 natural sciences010305 fluids & plasmasCoupling0103 physical sciencesMulti-physics approachGeneral Materials SciencePoint (geometry)Design point010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringCouplingRequirements engineeringbusiness.industryMechanical EngineeringNuclear powerFusion powerFinite element methodNuclear Energy and EngineeringHeat fluxBreeding blanketbusinessddc:600Fusion Engineering and Design
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Thermo-Mechanical Analysis and Design Update of the Top Cap Region of the DEMO Water-Cooled Lithium Lead Central Outboard Blanket Segment

2022

Within the framework of the EUROfusion research and development activities, the Water-Cooled Lithium Lead (WCLL) Breeding Blanket (BB) is one of the two candidates to be chosen as the driver blanket for the European DEMO nuclear fusion reactor. Hence, an intense research work is currently ongoing throughout the EU to develop a robust conceptual design able to fulfil the design requirements selected at the end of the DEMO pre-conceptual design phase. In this work, the thermo-mechanical analysis and the design update of the top cap (TC) region of the DEMO WCLL Central Out-board Blanket (COB) segment is presented. The scope of the work is to find a design solution of the WCLL COB TC region abl…

Fluid Flow and Transfer ProcessesTechnologyFEMQH301-705.5Thermo-mechanicsTPhysicsQC1-999Process Chemistry and TechnologyGeneral EngineeringDEMO; breeding blanket; WCLL; top cap; FEM; thermo-mechanicsEngineering (General). Civil engineering (General)Computer Science ApplicationsWCLLChemistryGeneral Materials ScienceBreeding blanketTA1-2040Biology (General)QD1-999InstrumentationDEMOSettore ING-IND/19 - Impianti NucleariTop cap
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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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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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Structural assessment of the EU-DEMO WCLL Central Outboard Blanket segment under normal and off-normal operating conditions

2021

Abstract Within the framework of the EUROfusion design activities concerning the EU-DEMO Breeding Blanket (BB) system, a research campaign has been carried out at the University of Palermo with the aim of investigating the structural behaviour of the DEMO Water-Cooled Lithium Lead (WCLL) Central Outboard Blanket (COB) segment. The assessment has been performed considering three different loading scenarios: the Normal Operation (NO), the Over-Pressurization (OP) and the Upward Vertical Displacement Event (VDE-up). In particular, NO scenario represents the loading case referring to the nominal operating conditions, whereas the OP scenario refers to the loading conditions due to an in-box LOCA…

business.industryDesign activitiesMechanical EngineeringFEM analysisStructural engineeringVDEBlanketPlasma volumeVertical motionFinite element methodWCLLNuclear Energy and EngineeringPlasma chamberGeneral Materials ScienceVertical displacementBreeding blanketbusinessDEMOGeologySettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringEvent (probability theory)
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Novel method for determination of tritium depth profiles in metallic samples

2019

Tritium accumulation in fusion reactor materials is considered a serious radiological issue, therefore a lot of effort has been concentrated on the development of radiometric techniques. A novel method, based on gradual dissolution, for the determination of the total tritium content and its depth profiles in metallic samples is demonstrated. This method allows for the measurement of tritium in metallic samples after their exposure to a hydrogen and tritium mixture, tritium containing plasma or after irradiation with neutrons resulting in tritium formation. In this method, successive layers of metal are removed using an appropriate etching agent in the controlled regime and the amount of evo…

inorganic chemicalsfusionNuclear and High Energy PhysicsMaterials scienceNuclear engineeringchemistry.chemical_elementheliumBlanket114 Physical sciences01 natural sciences010305 fluids & plasmasblanketMetalirradiated berylliumjet0103 physical sciencespolycyclic compounds010306 general physicsHeliumbreeding blanketJet (fluid)Fusiontritiumbehaviororganic chemicalshydrogen diffusiontemperatureiter-like-wallFusion powerfirst wallberylliumCondensed Matter Physicschemistryvisual_arttransportcardiovascular systemvisual_art.visual_art_mediumdepth profileTritiumBerylliumNuclear Fusion
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Preliminary thermal optimization and investigation of the overall structural behaviour of the EU-DEMO water-cooled lead lithium left outboard blanket…

2022

The conceptual design phase of the EU-DEMO reactor has been recently launched, with the aim of evolving the DEMO pre-conceptual layout towards a more robust and articulated geometric configuration able to cope with most of the design requirements and to show further margins for the passing of the current potential show-stoppers. Hence, the achievement of the conceptual design of the Water-Cooled Lead Lithium Breeding Blanket (WCLL BB) is one of the milestones the EUROfusion consortium aims to achieve in the close future. To this purpose, within the framework of the research activities promoted by EUROfusion, a research campaign has been launched at the University of Palermo, in close cooper…

ThermomechanicsLateral outboardNuclear Energy and EngineeringMechanical EngineeringDWTs optimizationFEM analysisGeneral Materials ScienceBreeding blanketSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringWCLL
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