0000000000012028

AUTHOR

A. Tincani

showing 19 related works from this author

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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Experimental tests and thermo-mechanical analyses on the HEXCALIBER mock-up

2008

Abstract Within the framework of the R&D activities promoted by European Fusion Development Agreement on the helium-cooled pebble bed test blanket module to be irradiated in ITER, ENEA Brasimone and the Department of Nuclear Engineering of the University of Palermo performed intense research activities on the modelling of the thermo-mechanical behaviour of both beryllium and lithiated ceramics pebble beds, which are envisaged to be used, respectively, as neutron multiplier and tritium breeder. In particular, at the DIN a thermo mechanical constitutive model was developed for both lithiated ceramics and beryllium pebble beds and it was successfully implemented on a commercial finite element …

Materials scienceStructural materialMechanical EngineeringNuclear engineeringConstitutive equationchemistry.chemical_elementBlanketFinite element methodPebble beds Thermo-mechanical constitutive model HCPB-TBMNuclear Energy and EngineeringchemistryMockupGeneral Materials ScienceNeutronBerylliumPebbleSettore ING-IND/19 - Impianti NucleariCivil and Structural Engineering
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Study of the thermo-mechanical performances of the IFMIF-EVEDA Lithium Test Loop target assembly

2012

Abstract Within the framework of the IFMIF R&D program and in close cooperation with ENEA-Brasimone, at the Department of Energy of the University of Palermo a research campaign has been launched to investigate the thermo-mechanical behavior of the target assembly under both steady state and start-up transient conditions. A theoretical approach based on the finite element method (FEM) has been followed and a well-known commercial code has been adopted. A realistic 3D FEM model of the target assembly has been set-up and optimized by running a mesh independency analysis. A proper set of loads and boundary conditions, mainly concerned with radiation heat transfer between the target assembly ex…

Steady stateMaterials scienceIFMIF Target assembly Thermo-mechanicsMechanical EngineeringNuclear engineeringLithium testFinite element methodLoop (topology)Hydrostatic testNuclear Energy and EngineeringHeat transferGeneral Materials ScienceTransient (oscillation)Boundary value problemSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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The HELICA mock-up. Experimental results and numerical thermo-mechanical analyses

2006

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Out of Pile Thermo-Mechanical Testing of Breeder Pebble Beds for HCPB TBM for ITER

2005

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A constitutive model for the thermo-mechanical behaviour of fusion-relevant pebble beds and its application to the simulation of HELICA mock-up exper…

2007

Abstract Within the framework of the R&D activities promoted by EFDA on the Helium-Cooled Pebble Bed Test Blanket Module to be irradiated in ITER, attention has been focused on the modelling of the thermo-mechanical behaviour of both beryllium and lithiated ceramic pebble beds that are envisaged to be used respectively as neutron multiplier and tritium breeder. This behaviour depends, mainly, on the reactor-relevant conditions, the pebble sizes and the breeder cell geometries and a general constitutive model has not yet been validated, especially for fusion-relevant applications. ENEA-Brasimone and the Department of Nuclear Engineering (DIN) of the University of Palermo have performed inten…

HCPB–TBMFusionMaterials scienceLithiated ceramic breederPebble-bed reactorMechanical EngineeringNuclear engineeringConstitutive equationThermo-mechanical constitutive modelBlanketFusion powerNuclear Energy and EngineeringMockupPebble bedGeneral Materials SciencePebbleThermo mechanicalSettore ING-IND/19 - Impianti NucleariCivil and Structural Engineering
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Final report on the test campaigns HELICA I-II performed in HEFUS facility

2005

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Updated design and integration of the ancillary circuits for the European Test Blanket Systems

2019

The validation of the key technologies relevant for a DEMO Breeding Blanket is one of the main objectives of the design and operation of the Test Blanket Systems (TBS) in ITER. In compliance with the main features and technical requirements of the parent breeding blanket concepts, the European TBM Project is developing the HCLL (Helium Cooled Lithium Lead) and HCPB (Helium Cooled Pebble Bed)-TBS, focusing in this phase on the design life cycle and on R&D activities in support of the design. The TBS ancillary systems are mainly circuits devoted to the removal of thermal power and to the extraction and recovery of the tritium generated in the Test Blanket Modules. They are: • The Helium C…

Computer scienceThermo-mechanical analysiTest Blanket ModuleBlanketCAD integration; Test Blanket Module; Thermo-hydraulic analysis; Thermo-mechanical analysis; Tritium technologies01 natural sciences7. Clean energy010305 fluids & plasmasTritium technologiesConceptual design0103 physical sciencesGeneral Materials Science010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringElectronic circuitThermo-hydraulic analysisThermo-mechanical analysisMechanical EngineeringCAD integrationCoolantTest (assessment)Nuclear Energy and EngineeringPhysical spaceSystems engineeringThermo-hydraulic analysiFusion Engineering and Design
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Hydraulic characterization of the full scale divertor cassette prototype

2011

In the frame of the activities related to ITER divertor R&D, ENEA C.R. Brasimone was in charge by Fusion For Energy (F4E) to perform the assembly, the hydraulic tests and the theoretical simulation of the hydraulic behavior of the full scale divertor cassette prototype. The objective of these activities was aimed at the investigation of the thermal-hydraulic behavior of the full-scale divertor cassette both under steady state condition and during draining and drying operational transient. In particular, the steady state tests were focused on finally check whether the hydraulic design of the divertor components is able to ensure a uniform and proper cooling for the plasma facing components, …

System codeNuclear Energy and EngineeringITER Divertor Draining and dryingMechanical EngineeringNuclear engineeringDivertorFull scaleEnvironmental scienceGeneral Materials ScienceTransient (oscillation)Settore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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On the theoretical–numerical study of the HEXCALIBER mock-up thermo-mechanical behaviour

2010

Abstract Within the framework of the R&D activities promoted by European Fusion Development Agreement on the Helium-Cooled Pebble Bed Test Blanket Module to be irradiated in ITER, ENEA Brasimone and the Department of Nuclear Engineering of the University of Palermo (DIN) performed intense research activities on the modelling of the thermo-mechanical behaviour of both beryllium and lithiated ceramics pebble beds, that are envisaged to be used, respectively, as neutron multiplier and tritium breeder. In particular, the DIN developed a thermo-mechanical constitutive model for these pebble beds to be validated against the HEXCALIBER mock-up test campaign, carried out at the ENEA HE-FUS3 facilit…

Materials scienceTokamakMechanical EngineeringNuclear engineeringchemistry.chemical_elementBlanketFusion powerFinite element methodlaw.inventionPebble beds Thermo-mechanical constitutive model HCPB-TBMNuclear Energy and EngineeringchemistryMockuplawGeneral Materials ScienceNeutronBerylliumPebbleSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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Preparation of HEXCALIBER tests and preliminary thermo-mechanical analyses

2006

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Maturation of critical technologies for the DEMO balance of plant systems

2022

The Pre-Concept Design (PCD) of the Balance of Plant (BoP) systems of the EU-DEMO power plant is described in this paper for both breeding blanket (BB) concepts under assessment, namely the Water Cooled Lithium Lead (WCLL) BB and the Helium Cooled Pebble Bed (HCPB) BB. Moreover, the results of a preliminary evaluation of a number of BoP variants are discussed. This paper outlines the steps of the BoP design development, highlighting the project objectives and the strategy for their achievement under the very challenging requirements which include, among others, the intermittent nature of the DEMO plasma heat source. The main achievements during the PCD Phase will be reported together with t…

TechnologyBalance of plantElectric power distributionMechanical EngineeringHCPB BBSteam generatorPower conversion systemPower plants -- Design and constructionNuclear Energy and EngineeringSteam-boilersGeneral Materials SciencePower-plants -- Europebalance of plant; DEMO; HCPB BB; power conversion system; steam generator; WCLL BBddc:600DEMOWCLL BBSettore ING-IND/19 - Impianti NucleariDEMO; Balance of plant; WCLL BB; HCPB BB; Steam generator; Power conversion systemCivil and Structural Engineering
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Steady state and transient thermal-hydraulic characterization of full-scale ITER divertor plasma facing components

2008

Abstract In the frame of the activities related to ITER divertor R&D, ENEA CR Brasimone was in charge by EFDA (European Fusion Development Agreement) to investigate the thermal-hydraulic behaviour of the full-scale divertor plasma facing components, i.e. the outer vertical target, the inner vertical target and the dome-liner, both in steady state and during draining and drying transient. The investigation was performed by means of both experimental test campaigns performed at ENEA CR Brasimone and theoretical simulation developed in RELAP5 Mod.3.3 environment at the Department of Nuclear Engineering of the University of Palermo (DIN). This paper presents the achieved experimental results fo…

Materials scienceSteady stateITER Divertor Plasma facing components Thermal-hydraulicsMechanical EngineeringNuclear engineeringDivertorFull scalePlasmaThermal hydraulicsNuclear Energy and EngineeringFUSIONE NUCLEARE ITER DIVERTORE TERMOIDRAULICAGeneral Materials ScienceTransient (oscillation)Settore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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Structural verification and manufacturing procedures of the cooling system, for DEMO divertor target (OVT)

2019

The paper presents the design activities and testing plan of a vertical target mock-up, developed within the pre-conceptual design phase for DEMO Work Package DIV-1 “Divertor Cassette Design and Integration” - EUROfusion Power Plant Physics & Technology (PPPT) program. Activities concerning the Divertor Outboard Vertical Target cooling mock-up are presented in term of CAD model, thermal-hydraulic numerical simulation, structural analysis, structural integrity verification and manufacturing procedure. Moreover, the mechanical dimensions of support systems for Plasma Facing Components (PFCs), manifold and diffuser have been analyzed in detail, in order to avoid structural fault during the tes…

Power stationComputer simulationDesign activitiesDivertor target cooling mock-upNuclear engineeringDivertorMechanical EngineeringDivertor cassetteCADFault (power engineering)01 natural sciences010305 fluids & plasmasNuclear Energy and Engineering0103 physical sciencesWater coolingDEMO; Divertor cassette; Divertor target cooling mock-up; Civil and Structural Engineering; Nuclear Energy and Engineering; Materials Science (all); Mechanical EngineeringGeneral Materials ScienceMaterials Science (all)Test plan010306 general physicsDEMO; Divertor cassette; Divertor target cooling mock-upDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural Engineering
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Conceptual design of the enhanced coolant purification systems for the European HCLL and HCPB test blanket modules

2019

Abstract The Coolant Purification Systems (CPSs) is one of the most relevant ancillary systems of European Helium Cooled Lead Lithium (HCLL) and Helium Cooled Pebble Bed (HCPB) Test Blanket Modules (TBMs) which are currently in the preliminary design phase in view of their installation and operation in ITER. The CPS implements mainly two functions: the extraction and concentration of the tritium permeated from the TBM modules into the primary cooling circuit and the chemistry control of helium primary coolant. During the HCLL and HCPB-TBSs (Test Blanket Systems) Conceptual Design Review (CDR) in 2015 it was recognized the need of reducing the tritium permeation into the Port Cell #16 of ITE…

Mechanical EngineeringNuclear engineeringCoolant purification systemBlanketTritium01 natural sciencesSizing010305 fluids & plasmasCoolantDesign phaseTBMNuclear Energy and EngineeringConceptual designITERCoolant purification system; ITER; TBM; Tritium0103 physical sciencesGeneral Materials Science010306 general physicsSettore 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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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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Optimization of the first wall for the DEMO water cooled lithium lead blanket

2015

The maximum heat load capacity of a DEMO First Wall (FW) of reasonable cost may impact the decision of the implementation of limiters in DEMO. An estimate of the engineering limit of the FW heat load capacity is an essential input for this decision. This paper describes the work performed to optimize the FW of the Water Cooled Lithium-Lead (WCLL) blanket concept for DEMO fusion reactor in order to increase its maximum heat load capacity. The optimization is based on the use of water at typical Pressurised Water Reactors conditions as coolant. The present WCLL FW with a waved plasma-faced surface and with circular channels was studied and the heat load limit has been predicted with FEM analy…

Work (thermodynamics)DesignMaterials scienceMechanical EngineeringNuclear engineeringDesign;DEMO;Blanket;WCLL;First WallFusion powerBlanketFinite element methodWCLLCoolantDesign for manufacturability[SPI]Engineering Sciences [physics]First WallDEMO Blanket WCLL Design First WallNuclear Energy and EngineeringThermalLimiterBlanketGeneral Materials ScienceDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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Pattern of cognitive impairment in systemic lupus erythematosus patients

2000

cognitive impairment systemic lupus erythematosusSettore MED/26 - Neurologia
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