0000000000023143

AUTHOR

R. Giammusso

showing 13 related works from this author

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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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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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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On the hyperporous non-linear elasticity model for fusion-relevant pebble beds

2010

Abstract Packed pebble beds are particular granular systems composed of a large amount of small particles, arranged in irregular lattices and surrounded by a gas filling interstitial spaces. Due to their heterogeneous structure, pebble beds have non-linear and strongly coupled thermal and mechanical behaviours whose constitutive models seem limited, being not suitable for fusion-relevant design-oriented applications. Within the framework of the modelling activities promoted for the lithiated ceramics and beryllium pebble beds foreseen in the Helium-Cooled Pebble Bed breeding blanket concept of DEMO, at the Department of Nuclear Engineering of the University of Palermo (DIN) a thermo-mechani…

Bulk modulusMaterials scienceDeformation (mechanics)Mechanical EngineeringIsotropyConstitutive equationPebble beds Mechanical constitutive model Non-linear elasticityModulusMechanicsElasticity (physics)Power lawNuclear Energy and EngineeringGeneral Materials SciencePebbleSettore ING-IND/19 - Impianti NucleariCivil and Structural Engineering
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On thermo-mechanical issues induced by irradiation swelling inside the back-plate of the IFMIF target assembly

2011

Abstract Within the framework of the IFMIF R&D program and in close cooperation with ENEA-Brasimone, at the Department of Nuclear Engineering of the University of Palermo a research campaign has been launched to investigate the thermo-mechanical issues potentially induced by irradiation swelling in the threaded connections between frame and back-plate of IFMIF target assembly. The main aim of the research campaign has relied in the assessment of the maximum swelling-induced volumetric strain that may be accepted in order to allow screws to withstand thermo-mechanical stresses and work in safe conditions or to avoid unduly high unscrewing torques during back-plate remotely handled maintenanc…

Parametric analysisComputer sciencebusiness.industryMechanical EngineeringFrame (networking)Structural engineeringFinite element methodNuclear Energy and EngineeringmedicineTorqueGeneral Materials ScienceBoundary value problemIrradiationSwellingmedicine.symptomIFMIF Irradiation swelling Threaded connection FEM analysisbusinessSettore ING-IND/19 - Impianti NucleariThermo mechanicalCivil and Structural EngineeringFusion Engineering and Design
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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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On the numerical assessment of the thermo-mechanical performances of the DEMO Helium-Cooled Pebble Bed breeding blanket module

2014

Within the framework of the European DEMO Breeder Blanket Programme, a research campaign has been launched by University of Palermo, ENEA-Brasimone and Karlsruhe Institute of Technology to theoretically investigate the thermo-mechanical behavior of the Helium-Cooled Pebble Bed (HCPB) breeding blanket module of the DEMO1 blanket vertical segment, under normal operation and over-pressurization loading 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. A realistic 3D FEM model of the HCPB blanket module central poloidal-radial region has been developed, inclu…

ToroidSteady stateThermo-mechanicsMechanical EngineeringNuclear engineeringHCBP blanketThermo-mechanicchemistry.chemical_elementDEMO reactorThermo-mechanics;DEMO reactor;HCBP blanketBlanketFinite element methodCoolantBreeder (animal)Nuclear Energy and EngineeringchemistryThermalDEMO reactor HCBP blanket Thermo-mechanicsEnvironmental scienceGeneral Materials ScienceSettore ING-IND/19 - Impianti NucleariHeliumCivil and Structural Engineering
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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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WCLL breeding blanket design and integration for DEMO 2015: status and perspectives

2017

Abstract Water-cooled lithium-lead breeding blanket is considered a candidate option for European DEMO nuclear fusion reactor. ENEA and the linked third parties have proposed and are developing a multi-module blanket segment concept based on DEMO 2015 specifications. The layout of the module is based on horizontal (i.e. radial-toroidal) water-cooling tubes in the breeding zone, and on lithium lead flowing in radial-poloidal direction. This design choice is driven by the rationale to have a modular design, where a basic geometry is repeated along the poloidal direction. The modules are connected with a back supporting structure, designed to withstand thermal and mechanical loads due to norma…

Neutron transportComputer scienceBlanket7. Clean energy01 natural sciencesbreeding blanket; CFD; DEMO; WCLL010305 fluids & plasmaslaw.inventionlaw0103 physical sciencesDesign choiceGeneral Materials Science010306 general physicsWCLL Breeding blanket DEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringWCLL Breeding blanket DEMObusiness.industryMechanical EngineeringLead systemPressurized water reactorFusion powerModular designNuclear Energy and EngineeringSystems engineeringbusinessTransport systemFusion Engineering and Design
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Structural analysis of the back supporting structure of the DEMO WCLL outboard blanket

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 outboard segment Back-Supporting Structure (BSS) of the DEMO Water-Cooled Lithium Lead breeding blanket (WCLL). In particular, the configuration of the outboard segment BSS, purposely set-up by the WCLL project team during 2015 according to the blanket “multi-module system” concept, has been taken into account in order to study its steady state thermo-mechanical behaviour, paying attention to the simulation of both modules-BSS and BSS-vacuum vessel…

Structure (mathematical logic)business.industryComputer scienceMechanical EngineeringDEMO reactor WCLL blanket BSSDEMO reactorStructural engineeringBlanket01 natural sciencesProject teamFinite element method010305 fluids & plasmasWCLL blanketGeometric designNuclear Energy and EngineeringLinearization0103 physical sciencesSafety criteriaGeneral Materials Science010306 general physicsbusinessBSSSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion 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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