Search results for "Coolant"

showing 10 items of 57 documents

Rewetting of a hot vertical surface by liquid sprays

2005

Hot surfaces rewetting interests several technological fields. A very important application is in nuclear reactors technology, where it governs the cooling of overheated fuel elements during hypothesized loss of coolant accidents (LOCAs). This phenomenon is also important in many normal processes and accidental situations taking place in conventional processes. For example when the integrity of metallic containers, filled by toxic or dangerous substances, is endangered by a hypothetical fire. The rewetting consists in the re-establishment of coolant in contact with metallic surfaces become dried due to high temperature. To this end cold liquid is injected on these surfaces via sprays or other …

Fluid Flow and Transfer ProcessesMechanical EngineeringGeneral Chemical EngineeringNuclear engineeringAerospace EngineeringCoolantSubcoolingNuclear Energy and EngineeringContainmentAccident managementloss of coolant accidents liquid sprays hot surface rewettingHeat transferEnvironmental scienceModel setSettore ING-IND/19 - Impianti NucleariCooling fluid
researchProduct

Characterization and thermomechanical assessment of a SiC-sandwich material for Flow Channel Inserts in DCLL blankets

2019

Abstract Flow Channel Inserts (FCIs) are key elements in the high-temperature Dual Coolant Lead Lithium (DCLL) blanket, since they insulate electrically the flowing PbLi to avoid MHD effects and protect the steel structure from the hot liquid metal. SiC-based materials are main candidates for high-temperature FCIs, being a dense-porous SiC-based sandwich material an attractive option. The present work is focused on the development of such a SiC-based material. On the one hand, in order to assess the suitability of the concept for FCIs, the main results of a stress analysis, MHD and heat transfer simulations are summarized. On the other hand, the experimental production of the SiC-based mate…

Liquid metalMaterials scienceMechanical EngineeringBlanketengineering.material7. Clean energy01 natural sciences010305 fluids & plasmasCoolantCorrosionStress (mechanics)Nuclear Energy and EngineeringCoatingFlexural strength0103 physical sciencesengineeringGeneral Materials ScienceComposite material010306 general physicsPorosityCivil and Structural EngineeringFusion Engineering and Design
researchProduct

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
researchProduct

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
researchProduct

On the thermal-hydraulic performances of the DEMO divertor cassette body cooling circuit equipped with a liner

2020

Abstract In the framework of the Work Package DIV 1 - “Divertor Cassette Design and Integration” of the EUROfusion action, a research campaign has been jointly carried out by University of Palermo and ENEA to investigate the steady-state thermal-hydraulic performances of the DEMO divertor cassette cooling system. The research activity has been focussed onto the most recent design of the Cassette Body (CB) cooling circuit, consistent with the DEMO baseline 2017 and equipped with a liner, whose main function is to protect the underlying vacuum pump CB opening from plasma radiation. The research campaign has been carried out following a theoretical-computational approach based on the finite vo…

Materials scienceNuclear engineeringComputational fluid dynamics01 natural sciences010305 fluids & plasmaslaw.inventionThermal hydraulicsDivertorlaw0103 physical sciencesWater coolingGeneral Materials ScienceTotal pressure010306 general physicsDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFinite volume methodThermofluid-dynamicsCassette bodybusiness.industryMechanical EngineeringDivertorCoolantNuclear Energy and EngineeringVacuum pumpbusinessCFD analysisFusion Engineering and Design
researchProduct

Thermal-hydraulic study of the DEMO divertor cassette body cooling circuit equipped with a liner and two reflector plates

2021

Abstract In the framework of the Work Package DIV 1 – “Divertor Cassette Design and Integration” of the EUROfusion action, a research campaign has been jointly carried out by University of Palermo and ENEA to investigate the steady-state thermal-hydraulic performances of the DEMO divertor cassette cooling system. The research activity has been focussed onto the most recent design of the Cassette Body (CB) cooling circuit, consistent with the DEMO baseline 2017 and equipped with a liner and two Reflector Plates (RPs), whose main functions are to protect the underlying vacuum pump hole from the radiation arising from plasma and shield the PFCs inlet distributors, respectively. The research ca…

Materials scienceNuclear engineeringComputational fluid dynamics7. Clean energy01 natural sciences010305 fluids & plasmaslaw.inventionThermal hydraulicsDivertorlawShield0103 physical sciencesWater coolingGeneral Materials Science010306 general physicsDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringThermofluid-dynamicsCassette bodybusiness.industryMechanical EngineeringDivertorCassette body CFD analysis DEMO Divertor Thermofluid-dynamicsCoolantNuclear Energy and EngineeringFlow velocityVacuum pumpbusinessCFD analysis
researchProduct

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
researchProduct

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
researchProduct

Thermal-hydraulic optimisation of the DEMO divertor cassette body cooling circuit equipped with a liner

2019

Abstract Within the framework of the Work Package DIV 1 - “Divertor Cassette Design and Integration” of the EUROfusion action, a research campaign has been jointly carried out by University of Palermo and ENEA to investigate the thermal-hydraulic performances of the DEMO divertor cassette cooling system. The research activity has been focused onto the most recent design of the Cassette Body (CB) cooling circuit equipped with a Liner, whose main function is to protect the underlying vacuum pump hole from the radiation arising from the plasma. The research campaign has been carried out following a theoretical-computational approach based on the Finite Volume Method and adopting the commercial…

Materials scienceNuclear engineeringThermofluid-dynamic7. Clean energy01 natural sciences010305 fluids & plasmaslaw.inventionThermal hydraulicsDivertorlaw0103 physical sciencesMass flow rateWater coolingGeneral Materials ScienceCFD analysi010306 general physicsDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringPressure dropThermofluid-dynamicsCassette bodyMechanical EngineeringDivertorCoolantNuclear Energy and EngineeringFlow velocityVacuum pumpFusion Engineering and Design
researchProduct

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)
researchProduct