Search results for "Water cooled"

showing 10 items of 14 documents

Further improvements of the water-cooled Pb–17Li blanket

2001

Abstract The water-cooled lithium–lead (WCLL) blanket is based on reduced-activation ferritic–martensitic steel as the structural material, the liquid alloy Pb–17Li as breeder and neutron multiplier, and water at typical PWR conditions as coolant. It was developed for DEMO specifications and shall be tested in ITER. In 1999, a reactor parameter optimization was performed in the EU which yielded improved specifications of what could be an attractive fusion power plant. Compared to DEMO, such a power reactor would be different in lay-out, size and performance, thus requiring to better exploit the potential of the WCLL blanket concept in conjunction with a water-cooled divertor. Several new ap…

Computer scienceMechanical EngineeringDivertorReference designWater cooledNuclear engineeringPower reactorFusion powerLiquid alloyBlanketCoolantNuclear physicsNuclear Energy and EngineeringGeneral Materials ScienceCivil and Structural EngineeringFusion Engineering and Design
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On the thermo-mechanical behaviour of DEMO water-cooled lithium lead equatorial outboard blanket module

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 DEMO water-cooled lithium lead breeding blanket (WCLL). In particular, attention has been paid to the most recent geometric configuration of the DEMO WCLL outboard equatorial module, as designed by WCLL project team during 2015, endowed with an attachment system based on the use of radial pins, purposely outlined to connect the module back-plate to its back-supporting structure, that have been properly considered to simulate more realistically the …

Computer scienceMechanical EngineeringWater cooledGeometric configurationDEMO reactor WCLL blanket Lithium-lead Thermo-mechanicsMechanical engineeringBlanket01 natural sciencesFinite element method010305 fluids & plasmasNuclear Energy and EngineeringCabin pressurizationLinearization0103 physical sciencesGeneral Materials Science010306 general physicsSettore ING-IND/19 - Impianti NucleariThermo mechanicalCivil and Structural EngineeringFusion Engineering and Design
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Parametric thermal analysis for the optimization of Double Walled Tubes layout in the Water Cooled Lithium Lead inboard blanket of DEMO fusion reactor

2019

Abstract Within the roadmap that will lead to the nuclear fusion exploitation for electric energy generation, the construction of a DEMOnstration (DEMO) reactor is, probably, the most important milestone to be reached since it will demonstrate the technological feasibility and economic competitiveness of an industrial-scale nuclear fusion reactor. In order to reach this goal, several European universities and research centres have joined their efforts in the EUROfusion action, funded by HORIZON 2020 UE programme. Within the framework of EUROfusion research activities, ENEA and University of Palermo are involved in the design of the Water-Cooled Lithium Lead Breeding Blanket (WCLL BB), that …

HistoryNuclear Fusion Blanket Liquid Metal Thermal AnalysisDouble walledMaterials scienceNuclear engineeringWater cooledchemistry.chemical_element02 engineering and technologyFusion powerBlanket021001 nanoscience & nanotechnology01 natural sciences7. Clean energy010305 fluids & plasmasComputer Science ApplicationsEducationchemistry0103 physical sciencesLithium0210 nano-technologyLead (electronics)Thermal analysisSettore ING-IND/19 - Impianti NucleariParametric statisticsJournal of Physics: Conference Series
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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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Neutronic and photonic analysis of the single box water-cooled lithium lead blanket for a DEMO reactor

1998

Abstract The water-cooled Pb–17Li demonstration plant (DEMO) breeding blanket line was selected in 1995 as one of the two EU lines to be further developed in the next decade. In this paper the results of a neutronic and photonic analysis of the `single box' concept is presented. A full three-dimensional model, including the whole assembly and many of the DEMO reactor components, has been developed, together with a three-dimensional neutron source. A tritium breeding ratio (TBR) value of 1.16, with no ports and a Li6 enrichment of 90%, has been obtained and a further analysis has been performed to determine Li6 enrichment that would still ensure tritium breeding self-sufficiency. Selected po…

Materials scienceHelium gasbusiness.industryMechanical EngineeringWater cooledNuclear engineeringchemistry.chemical_elementBlanketNuclear physicsLead (geology)Nuclear Energy and EngineeringchemistryElectromagnetic shieldingNeutron sourceGeneral Materials ScienceLithiumPhotonicsbusinessCivil and Structural EngineeringFusion 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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Water-cooled Pb–17Li test blanket module for ITER: Impact of the structural material grade on the neutronic responses

1998

Abstract The Water-Cooled Lithium Lead (WCLL) DEMO blanket is one of the two EU lines to be further developed with the aim of manufacturing by 2010 a Test Blanket Module for ITER (TBM). In this paper results of a 3D-Monte Carlo neutronic analysis of the TBM design are reported. A fully 3D heterogeneous model of the WCLL–TBM has been inserted into an existing ITER model accounting for a proper D–T neutron source. The structural material assumed for the calculations was martensitic 9% Cr steel code named Z 10 CDV Nb 9-1. Results have been compared with those obtained using MANET. The main nuclear responses of the TBM have been determined, such as detailed power deposition density, material da…

Nuclear and High Energy PhysicsStructural materialChemistryNuclear engineeringWater cooledPower depositionchemistry.chemical_elementBlanketNuclear physicsNuclear Energy and EngineeringNeutron sourceGeneral Materials ScienceTritiumLithiumProduction rateJournal of Nuclear Materials
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Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System

2021

Abstract The Water Cooled Lithium Lead Test Blanket System (WCLL TBS) is one of the EU Test Blanket Systems candidate for being installed and operated in ITER. In view of its Conceptual Design Review by F4E and ITER Organization (IO), planned for mid-September 2020, several technical activities have been performed in the areas of WCLL TBS Ancillary Systems design. In this article the outcomes of the conceptual design phase of the four main Ancillary Systems of WCLL TBS, namely the Water Cooling System (WCS), the Coolant Purification System (CPS), the PbLi loop and the Tritium Extraction System (TES), are reported and critically discussed. In particular, for each Ancillary System hereafter a…

Nuclear engineeringCPS; ITER; PbLi loop; TES; WCLL TBS; WCSchemistry.chemical_elementPbLi loopBlanket01 natural sciences010305 fluids & plasmasConceptual designITER0103 physical sciencesWater coolingGeneral Materials Science010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringMechanical EngineeringWater cooledCoolantNuclear Energy and EngineeringchemistryEnvironmental scienceSystems designLithiumCPSWCSTESWCLL TBS
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Preliminary design of the top cap of DEMO Water-Cooled Lithium Lead breeding blanket segments

2020

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 preliminary design the top cap foreseen for the DEMO Water-Cooled Lithium Lead (WCLL) breeding blanket segments. Due to the high heat and pressure loads acting on such component, its design results particularly demanding and a specific multi-physics approach is needed, covering several aspects from thermal-hydraulics to structural assessments. Preliminary detailed CAD model of the cap integrated into the upper region of the WCLL breeding blanket outboard central segment has been set-up, equipped with proper cooling …

Nuclear engineeringchemistry.chemical_elementBlanket7. Clean energy01 natural sciencesTop cap010305 fluids & plasmasLead (geology)Component (UML)0103 physical sciencesGeneral Materials Science010306 general physicsDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringElectronic circuitStructural materialMechanical EngineeringWater cooledCapWCLLNuclear Energy and EngineeringchemistryEnvironmental scienceMulti-physicsLithiumBreeding blanketFusion Engineering and Design
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Multiphysics Optimization for First Wall Design Enhancement in Water-Cooled Breeding Blankets

2021

Abstract The commercial feasibility of the first fusion power plant generation adopting D-T plasma is strongly dependent upon the self-sustainability in terms of tritium fuelling. Within such a kind of reactor, the component selected to house the tritium breeding reactions is the breeding blanket, which is further assigned to heat power removal and radiation shielding functions. As a consequence of both its role and position, the breeding blanket is heavily exposed to both surface and volumetric heat loads and, hence, its design requires a typical multiphysics approach, from the neutronics to the thermo-mechanics. During last years, a great deal of effort has been put in the optimization of…

OptimizationNuclear and High Energy PhysicsNeutron transportBreeding blanket Complex method Multiphysics Neutronics Optimization ThermomechanicsComputer scienceMaterials Science (miscellaneous)Water cooledMultiphysicsNuclear engineeringMultiphysicsTK9001-9401Structural integrityMaximizationBlanketFusion powerComplex methodThermomechanicsNuclear Energy and EngineeringComponent (UML)NeutronicsNuclear engineering. Atomic powerBreeding blanketSettore ING-IND/19 - Impianti Nucleari
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