Search results for "Thermal hydraulics"

showing 10 items of 25 documents

Analysis of Protected Accidental Transients in the EFIT Reactor With the RELAP5 Thermal-Hydraulic Code

2008

The European Facility for Industrial Transmutation (EFIT) is aimed at demonstrating the feasibility of transmutation process through the Accelerator Driven System (ADS) route on an industrial scale. The conceptual design of this reactor of about 400 MW thermal power is under development in the frame of the European EUROTRANS Integrated Project of the EURATOM Sixth Framework Program (FP6). EFIT is a pool-type reactor cooled by forced circulation of lead in the primary system where the heat is removed by steam generators installed inside the reactor vessel. The reactor power is sustained by a spallation neutron source supplied by a proton beam impinging on a lead target at the core centre. A …

EFIT reactor RELAP5 thermal-hydraulic code protected accidental transientsEngineeringNuclear transmutationWaste managementbusiness.industryNuclear engineeringThermal power stationHeat sinkThermal hydraulicsNatural circulationDecay heatbusinessReactor pressure vesselSettore ING-IND/19 - Impianti NucleariThermal energyVolume 3: Thermal Hydraulics; Instrumentation and Controls
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Progress in the initial design activities for the European DEMO divertor: Subproject "Cassette"

2017

Abstract Since 2014 preconceptual design activities for European DEMO divertor have been conducted as an integrated, interdisciplinary R&D effort in the framework of EUROfusion Consortium. Consisting of two subproject areas, ‘Cassette’ and ‘Target’, this divertor project has the objective to deliver a holistic preconceptual design concept together with the key technological solutions to materialize the design. In this paper, a brief overview on the recent results from the subproject ‘Cassette’ is presented. In this subproject, the overall cassette system is engineered based on the load analysis and specification. The preliminary studies covered multi-physical analyses of neutronic, thermal,…

EngineeringDesign activitiesNeutronic01 natural sciences7. Clean energy010305 fluids & plasmasThermal hydraulicsMaterials Science(all)0103 physical sciencesNeutronicsGeneral Materials Science010306 general physicsDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFocus (computing)business.industryDivertorMechanical EngineeringDEMO; Divertor cassette; Neutronics; Cooling; Thermohydraulics; Electromagnetic loadsDivertor cassetteThermohydraulicNuclear Energy and EngineeringDEMO Divertor cassette Neutronics Cooling Thermohydraulics Electromagnetic loadsSystems engineeringLoad analysisCooling; DEMO; Divertor cassette; Electromagnetic loads; Neutronics; Thermohydraulics; Civil and Structural Engineering; Nuclear Energy and Engineering; Materials Science (all); Mechanical EngineeringElectromagnetic loadsMaterials Science (all)businessThermohydraulicsCooling
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TRACE Code Analyses for the IAEA ICSP on “Integral PWR Design Natural Circulation Flow Stability and Thermo-Hydraulic Coupling of Containment and Pri…

2011

Considering the world energy demand increase in order to fulfill an environmental and economic sustainability, the energy policy of each country has to diversify the sources of energy and use stable, safe energy production option able of producing electricity in a clean way contributing in cutting the CO2 emission. In the framework of the sustainable development, today the use of advanced nuclear power plant, have an important role in the environmental and economic sustainability of country energy strategy. In the last 20 years, in fact, the international community, taking into account the operational experience of the nuclear reactors, starts the development of new advanced reactor designs…

Engineeringbusiness.industryNuclear engineeringBoiler feedwaterBoiler (power generation)MASLWR SMR IAEA ICSP Primary/Containment Coupling Natural Circuationlaw.inventionThermal hydraulicsNatural circulationlawNuclear power plantLight-water reactorbusinessReactor pressure vesselBoiler blowdownSettore ING-IND/19 - Impianti NucleariSimulationASME 2011 Small Modular Reactors Symposium
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Analyses of the OSU-MASLWR Experimental Test Facility

2012

Today, considering the sustainability of the nuclear technology in the energy mix policy of developing and developed countries, the international community starts the development of new advanced reactor designs. In this framework, Oregon State University (OSU) has constructed, a system level test facility to examine natural circulation phenomena of importance to multi-application small light water reactor (MASLWR) design, a small modular pressurized water reactor (PWR), relying on natural circulation during both steady-state and transient operation. The target of this paper is to give a review of the main characteristics of the experimental facility, to analyse the main phenomena characteri…

Engineeringbusiness.industryNuclear engineeringPressurized water reactorOSU-MASLWR natural circulation modular PWRExperimental dataEnergy mixModular designnatural circulationlaw.inventionThermal hydraulicsNuclear technologyNatural circulationNuclear Energy and EngineeringlawLight-water reactorlcsh:Electrical engineering. Electronics. Nuclear engineeringOSU-MASLWRmodular PWRbusinesslcsh:TK1-9971Settore ING-IND/19 - Impianti NucleariSimulationMASLWR SMR Best Estimate Thermal Hydraulic System Code Helical Coil Steam Generator Primary/Containment Coupling Natural CircuationScience and Technology of Nuclear Installations
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Numerical simulation of the transient thermal-hydraulic behaviour of the ITER blanket cooling system under the draining operational procedure

2015

Abstract Within the framework of the research and development activities supported by the ITER Organization on the blanket system issues, an intense analysis campaign has been performed at the University of Palermo with the aim to investigate the thermal-hydraulic behaviour of the cooling system of a standard 20° sector of ITER blanket during the draining transient operational procedure. The analysis has been carried out following a theoretical-computational approach based on the finite volume method and adopting the RELAP5 system code. In a first phase, attention has been focused on the development and validation of the finite volume models of the cooling circuits of the most demanding mod…

Finite volume methodRELAP5Computer simulationMechanical EngineeringNuclear engineeringBlanketCoolantThermal hydraulicsblanketNuclear Energy and EngineeringThermal-hydraulicWater coolingThermal-hydraulic RELAP5 Draining BlanketEnvironmental scienceGeneral Materials ScienceTransient (oscillation)drainingSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringElectronic circuit
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Analysis of steady state thermal-hydraulic behaviour of the DEMO Divertor cassette body cooling circuit

2017

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 ENEA and University of Palermo to investigate the thermal-hydraulic performances of the DEMO divertor cassette cooling system. A comparative evaluation study has been performed considering the two different options under consideration for the divertor cassette body coolant, namely subcooled pressurized water and helium. The research activity has been carried out following a theoretical-computational approach based on the finite volume method and adopting a qualified Computational Fluid-Dynamic (CFD) code. CFD analy…

Finite volume methodSteady statebusiness.industryMechanical EngineeringNuclear engineeringDivertorComputational fluid dynamicsDEMO Divertor Cassette body CFD analysisThermofluid-dynamics7. Clean energy01 natural sciences010305 fluids & plasmasCoolantSubcoolingThermal hydraulicsMaterials Science(all)Nuclear Energy and Engineering0103 physical sciencesWater coolingEnvironmental scienceGeneral Materials Science010306 general physicsbusinessSettore ING-IND/19 - Impianti NucleariCivil and Structural Engineering
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RELAP5-3D thermal hydraulic analysis of the target cooling system in the SPES experimental facility

2014

The SPES (Selective Production of Exotic Species) experimental facility, under construction at the Italian National Institute of Nuclear Physics (INFN) Laboratories of Legnaro, Italy, is a second generation Isotope Separation On Line (ISOL) plant for advanced nuclear physic studies. The UCx target-ion source system works at temperature of about 2273 K, producing a high level of radiation (10^5 Sv/h), for this reason a careful risk analysis for the target chamber is among the major safety issues. In this paper, the obtained results of thermofluid-dynamics simulations of accidental transients in the SPES target cooling system are reported. The analysis, performed by using the RELAP5-3D 2.4.2 …

HistoryEngineeringSystem codeRELAP5target cooling systemthermo-fluid-dynamics simulationbusiness.industrySource systemNuclear engineeringMechanical engineeringSPESsafety analysiComputer Science ApplicationsEducationIsotope separationlaw.inventionThermal hydraulicsPhysics and Astronomy (all)RELAP5; safety analysis; SPES; target cooling system; thermo-fluid-dynamics simulations; Physics and Astronomy (all)lawWater coolingbusinessSettore ING-IND/19 - Impianti Nucleari
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Analysis of a full-scale integral test in PERSEO facility by using TRACE code

2017

Over the last decades a lot of experimental researches have been done to increase the reliability of passive decay heat removal systems implementing in-pool immersed heat exchanger. In this framework, a domestic research program on innovative safety systems was carried out leading the design and the development of the PERSEO facility at the SIET laboratories. The configuration of the system consists of an heat exchanger contained in a small pool which is connected both at the bottom and at the top to a large water reservoir pool. Within the frame of a national research program funded by the Italian minister of economic development, the DEIM department of the University of Palermo in coopera…

HistoryPERSEO Validation TRACE Thermal-hydraulics Passive safety systemsPhysics -- ExperimentsHeat exchangersComputer scienceNuclear engineeringFrame (networking)Full scaleExperimental dataSystem safetyComputer Science ApplicationsEducationThermal hydraulicsEconomic development -- ItalyHeat exchangerDecay heatTRACE (psycholinguistics)
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Thermal-hydraulic and thermo-mechanical simulations of Water-Heavy Liquid Metal interactions towards the DEMO WCLL breeding blanket design

2019

Abstract The Water-Cooled Lithium Lead breeding blanket concept foresees the eutectic lithium-lead (Pb-15.7Li) alloy being cooled by pressurized sub-cooled water (temperature 295–328 °C; pressure 15.5 MPa) flowing in double wall tubes. Therefore, the interaction between the Pb-15.7Li and water (e.g. tube rupture) represents one of the main safety concerns for the design and safety analysis. Available LIFUS5/Mod2 experimental data are employed to assess the performances of thermal-hydraulic and thermo-mechanic codes. Thermal-hydraulic simulations, by SIMMER-III code, are focused on the prediction of the thermodynamic interaction among the fluids. ABAQUS Finite Element code, used for the desi…

Liquid metalMaterials scienceNuclear engineeringchemistry.chemical_elementBlanket01 natural sciences010305 fluids & plasmasThermal hydraulics0103 physical sciencesGeneral Materials ScienceTube (fluid conveyance)010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringEutectic systemMechanical EngineeringStress–strain curveWater-Liquid metal interactionExperimental dataBreeding blanket; LIFUS5; Water-Liquid metal interactionsWater-Liquid metal interactionsNuclear Energy and EngineeringchemistryLithiumBreeding blanketLIFUS5
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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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