Search results for "fusion"

showing 10 items of 4513 documents

Analysis of the thermo-mechanical behaviour of IFMIF Target Assembly

2013

Target Assembly Thermo-mechanicsIFMIFNUCLEAR FUSION IFMIFSettore ING-IND/19 - Impianti Nucleari
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Two-dimensional parametric parenchymal blood flow in transarterial chemoembolisation for hepatocellular carcinoma: perfusion change quantification an…

2020

Aim To evaluate the feasibility and potential value of two-dimensional (2D) parametric parenchymal blood flow (2D-PPBF) for the assessment of perfusion changes during transarterial chemoembolisation with drug-eluting beads (DEB-TACE) and to analyse correlations of 2D-PPBF parameters and tumour response. Materials and methods Thirty-two patients (six women, 26 men, mean age: 67±8.9 years) with unresectable hepatocellular carcinoma (HCC) who underwent their first DEB-TACE were included in this study. To quantify perfusion changes using 2D-PPBF, the acquired digital subtraction angiography (DSA) series were post-processed. Ratios were calculated between the reference region of interest (ROI) a…

Target lesionMaleCarcinoma HepatocellularWilcoxon signed-rank test030218 nuclear medicine & medical imagingPost-intervention03 medical and health sciences0302 clinical medicinemedicineHumansRadiology Nuclear Medicine and imagingChemoembolization TherapeuticAgedRetrospective Studiesmedicine.diagnostic_testbusiness.industryLiver NeoplasmsArea under the curveAngiography Digital SubtractionGeneral MedicineDigital subtraction angiographyBlood flowmedicine.diseaseTreatment OutcomeLiver030220 oncology & carcinogenesisHepatocellular carcinomaFemaleNuclear medicinebusinessPerfusionFollow-Up StudiesClinical radiology
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Experimental Studies on the Influence of Surfactants on Intestinal Absorption of Drugs Cefadroxil as model drug and sodium taurocholate as natural mo…

2011

The influence of the natural bile acid surfactant sodium taurocholate (CAS 81-24-3) on colic and duodenal (i.e. the proximal third of the small intestine) absorption of cefadroxil (CAS 50370-12-2) was studied using the in situ rat gut technique, and compared with the effect of sodium lauryl sulfate (CAS 151-21-3), the most widely used synthetic anionic surfactant. Previously, the stability, compatibility, and micelle-solubilization characteristics of taurocholate were assessed in order to correct, when necessary, the absorption results. White the passive absorption rate constants (kf, h-1) determined in colon in the presence of increasing lauryl sulfate concentrations showed an asymptotic v…

Taurocholic AcidColonDuodenumSodiumBiological Availabilitychemistry.chemical_elementModels BiologicalMicelleIntestinal absorptionSurface-Active AgentsPulmonary surfactantDrug DiscoverymedicineAnimalsMicellesAntibacterial agentChromatographyChemistryCefadroxilHydrogen-Ion ConcentrationSmall intestineCephalosporinsRatsBioavailabilityPerfusionmedicine.anatomical_structureIntestinal AbsorptionCefadroxilAlgorithmsChromatography Liquidmedicine.drugArzneimittelforschung
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Les fusions de sociétés : régimes juridique et fiscal

2012

National audience; ...

TaxationDroit[SHS.GESTION]Humanities and Social Sciences/Business administrationFrance[ SHS.GESTION ] Humanities and Social Sciences/Business administration[SHS.GESTION] Humanities and Social Sciences/Business administrationConsolidation and merger of corporationsComputingMilieux_MISCELLANEOUSFusion d'entreprisesLaw and legislationImpôts
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Divertor of the European DEMO: Engineering and technologies for power exhaust

2022

International audience; In a power plant scale fusion reactor, a huge amount of thermal power produced by the fusion reaction and external heating must be exhausted through the narrow area of the divertor targets. The targets must withstand the intense bombardment of the diverted particles where high heat fluxes are generated and erosion takes place on the surface. A considerable amount of volumetric nuclear heating power must also be exhausted. To cope with such an unprecedented power exhaust challenge, a highly efficient cooling capacity is required. Furthermore, the divertor must fulfill other critical functions such as nuclear shielding and channeling (and compression) of exhaust gas fo…

Technology020209 energyMechanical EngineeringPower exhaust02 engineering and technologyDEMO; Fusion reactor; Divertor; Plasma-facing component; High-heat-flux; Power exhaust01 natural sciences7. Clean energy010305 fluids & plasmas[SPI]Engineering Sciences [physics]Fusion reactorDivertorDEMO; Divertor; Fusion reactor; High-heat-flux; Plasma-facing component; Power exhaustNuclear Energy and Engineering0103 physical sciences0202 electrical engineering electronic engineering information engineeringPlasma-facing componentGeneral Materials ScienceHigh-heat-fluxddc:600DEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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Preliminary thermal-hydraulic analysis of the EU-DEMO Helium-Cooled Pebble Bed fusion reactor by using the RELAP5-3D system code

2021

Abstract In the frame of the activities promoted and encouraged by the EUROfusion Consortium aimed at developing the EU-DEMO fusion reactor, great emphasis has been placed at a very early stage of the design to incorporate the provisions needed to improve the overall plant safety and reliability performances as well as to analyse possible mitigation actions. In this framework, the research activity has been focused on the representative and safety relevant cooling loop of the Helium Cooled Pebble Bed (HCPB) Breeding Blanket (BB) Primary Heat Transfer System (PHTS), purposely selected by the safety team, in order to assess its thermal-hydraulic behaviour during normal operational conditions …

TechnologyComputer science020209 energyNuclear engineeringHCPBchemistry.chemical_element02 engineering and technologyBlanket7. Clean energy01 natural sciences010305 fluids & plasmasThermal hydraulicsReliability (semiconductor)0103 physical sciences0202 electrical engineering electronic engineering information engineeringGeneral Materials ScienceRELAP5-3DSafety and EnvironmentHeliumSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringSteady stateFinite volume methodMechanical EngineeringFusion powerEU-DEMONuclear Energy and EngineeringchemistryThermal-hydraulicsHeat transferddc:600
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In Situ Regeneration of Copper-Coated Gas Diffusion Electrodes for Electroreduction of CO2 to Ethylene

2021

This research was funded by the European Union’s Horizon 2020 research and innovation program under grant agreement No 768789 as well as by the Polish National Centre of Science under grant no 2017/26/D/ST8/00508. The Institute of Solid State Physics, University of Latvia, as a center of excellence, has received funding from the European Union’s Horizon 2020 Framework Programme H2020-WIDESPREAD-01-2016-2017-TeamingPhase2 under grant agreement no. 739508, project CAMART2.

TechnologyEthyleneInorganic chemistrychemistry.chemical_element02 engineering and technologyElectrolyte010402 general chemistryElectrocatalyst7. Clean energy01 natural sciencesArticleCatalysischemistry.chemical_compoundEthyleneCopper catalystsethyleneelectrocatalysisGaseous diffusionGeneral Materials Sciencecopper complexesElectrochemical reduction of carbon dioxideMicroscopyQC120-168.85TQH201-278.5carbon dioxideEngineering (General). Civil engineering (General)021001 nanoscience & nanotechnologyCopperTK1-99710104 chemical sciencesDescriptive and experimental mechanicschemistryCarbon dioxide13. Climate action:NATURAL SCIENCES [Research Subject Categories]copper catalystsElectrical engineering. Electronics. Nuclear engineeringTA1-2040GDE0210 nano-technologyElectrocatalysisFaraday efficiencyCopper complexes
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Identification of blanket design points using an integrated multi-physics approach

2017

Abstract The breeding blanket (BB) is one of the key components for a fusion reactor. It is expected to sustain and remove considerable heat loads due to the heat flux coming from the plasma and the nuclear power deposited by the fusion neutrons. In the design of the BB, the engineering requirements of nuclear, material and safety kind are involved. In the European DEMO project, several efforts are dedicated to the development of an integrated simulation-design tool able to perform a multi-physics analysis, allowing the characterisation of BB design points which are consistent from the neutronic, thermal-hydraulic and thermo-mechanical point of view. Furthermore, at Karlsruhe Institute of T…

TechnologyNuclear engineeringDEMO reactorBlanket7. Clean energy01 natural sciences010305 fluids & plasmasCoupling0103 physical sciencesMulti-physics approachGeneral Materials SciencePoint (geometry)Design point010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringCouplingRequirements engineeringbusiness.industryMechanical EngineeringNuclear powerFusion powerFinite element methodNuclear Energy and EngineeringHeat fluxBreeding blanketbusinessddc:600Fusion Engineering and Design
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Integrated design of breeding blanket and ancillary systems related to the use of helium or water as a coolant and impact on the overall plant design

2021

Currently, for the EU DEMO, two Breeding Blankets (BBs) have been selected as potential candidates for the integration in the reactor. They are the Water Cooled Lithium Lead and the Helium Cooled Pebble Bed BB concepts. The two BB variants together with the associated ancillary systems drive the design of the overall plant. Therefore, a holistic investigation of integration issues derived by the BB and the installation of its ancillary systems has been performed. The issues related to the water activation due to the 16N and 17N isotopes and the impact on the primary heat transfer systems have been investigated providing guidelines and dedicated solution for the integration of safety devices…

TechnologyNuclear engineeringintegration issuesBreeding blanket; Integration issues; Water activation; Tritium management; VVPSSchemistry.chemical_elementIsolation valveSystem safetyBlanketTritium01 natural sciences010305 fluids & plasmasVVPSS0103 physical sciencesFusion reactors -- Design and constructionGeneral Materials Science010306 general physicswater activationSettore ING-IND/19 - Impianti NucleariHeliumCivil and Structural EngineeringIntegrated designbreeding blanket; integration issues; tritium management; VVPSS; water activationbreeding blanketMechanical EngineeringWater -- Thermal propertiesCoolanttritium managementNuclear Energy and EngineeringchemistryHeat transferEnvironmental scienceHelium -- Thermal propertiesPlant designddc:600Power-plants -- Design and construction
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The DEMO water-cooled lead–lithium breeding blanket: design status at the end of the pre-conceptual design phase

2021

The Water-Cooled Lead–Lithium Breeding Blanket (WCLL BB) is one of the two blanket concept candidates to become the driver blanket of the EU-DEMO reactor. The design was enacted with a holistic approach. The influence that neutronics, thermal-hydraulics (TH), thermo-mechanics (TM) and magneto-hydro-dynamics (MHD) may have on the design were considered at the same time. This new approach allowed for the design team to create a WCLL BB layout that is able to comply with different foreseen requirements in terms of integration, tritium self-sufficiency, and TH and TM needs. In this paper, the rationale behind the design choices and the main characteristics of the WCLL BB needed for the EU-DEMO …

TechnologyQH301-705.5QC1-99901 natural sciences010305 fluids & plasmas0103 physical sciencesGeneral Materials ScienceBiology (General)010306 general physicsInstrumentationQD1-999DEMOSettore ING-IND/19 - Impianti Nuclearinuclear fusionFluid Flow and Transfer Processesbreeding blanketProcess Chemistry and TechnologyTPhysicsGeneral EngineeringDEMO; nuclear fusion; breeding blanket; nuclear reactorEngineering (General). Civil engineering (General)Computer Science ApplicationsChemistrynuclear reactorTA1-2040
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