Search results for "nuclear energy"

showing 10 items of 614 documents

Radiation stability of long-term annealed bi-phasic advanced ceramic breeder pebbles

2019

Abstract Advanced ceramic breeder pebbles consisting of Li4SiO4 and additions of Li2TiO3 were tested regarding their long-term thermal and to their radiation stability. As-prepared and long-term annealed pebbles were irradiated with accelerated electrons (up to 6 MGy) to investigate the formation of radiation-induced defects and radiolysis products caused by ionizing radiation. By using Raman spectroscopy the formation of significant amounts of radiolysis products can be excluded. Electron spin resonance spectrometry revealed several paramagnetic radiation-induced defects, such as HC2 centres ( SiO 4 3 - and TiO 3 - ), E’ centres ( SiO 3 3 - and TiO 3 3 - ), Ti 3 + centres and peroxide radi…

Materials scienceMechanical EngineeringRadicalAnalytical chemistry01 natural sciences010305 fluids & plasmasIonizing radiationlaw.inventionsymbols.namesakeNuclear Energy and Engineeringlawvisual_art0103 physical sciencesRadiolysisvisual_art.visual_art_mediumsymbolsGeneral Materials ScienceCeramicIrradiation010306 general physicsLuminescenceElectron paramagnetic resonanceRaman spectroscopyCivil and Structural EngineeringFusion Engineering and Design
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Thermoluminescence study of irradiated lithium orthosilicate

1998

Abstract The thermoluminescental investigations of neutron and gamma irradiated lithium orthosilicate pellets were carried out. It has been shown that the addition of Cr 3+ and Fe 3+ ions with the total concentration up to 2.0 wt.% during preparation of lithium orthosilicate pellets, significantly reduces the formation of radiation defects in irradiated matrix. This phenomena can be explained by the reducing of the formation of primary radiation defects during irradiation due to stimulating the recombination processes by the ions of impurities. Several ion concentration combinations were studied. The thermoluminescental investigations of fast neutron irradiated lithium orthosilicate pellets…

Materials scienceMechanical EngineeringRadiochemistryPelletschemistry.chemical_elementThermoluminescenceIonchemistry.chemical_compoundNuclear Energy and EngineeringchemistryGeneral Materials ScienceNeutronLithiumIrradiationLithium oxideOrthosilicateCivil and Structural EngineeringFusion Engineering and Design
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Study of tritium and helium generation and release from lead-lithium eutectics Li15.7Pb under neutron irradiation

2019

Abstract This paper describes the experiments on study of tritium and helium generation and release processes from lead-lithium eutectics Li15.7Pb. The irradiation was performed at the IVG.1M research reactor at 6 MW of thermal power. The irradiation temperature increased step by step from 225 to 550 °C. A qualitative assessment of the experimental results showed that as the temperature rises above 390 °C, the tritium flux from the sample consisting of T2 and HT molecules decreases. It was concluded that the observed effect is similar to the previously observed one for lead-lithium eutectics with Li17Pb83 composition.

Materials scienceMechanical EngineeringRadiochemistrychemistry.chemical_element01 natural sciences010305 fluids & plasmasFlux (metallurgy)Nuclear Energy and Engineeringchemistry0103 physical sciencesGeneral Materials ScienceLithiumTritiumResearch reactorIrradiation010306 general physicsLead (electronics)HeliumCivil and Structural EngineeringEutectic systemFusion Engineering and Design
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Effects of external energetic factors on tritium release from the EXOTIC 8-3/13 neutron-irradiated beryllium pebbles

2009

Abstract Tritium release from samples of 9–13 mg of the EXOTIC 8-3/13 neutron-irradiated beryllium pebbles under the separate and simultaneous action of temperature 490–770 K, 5 MeV fast-electron radiation 14 MGy h−1 for 3 h and magnetic field (MF) of 1.7 T was investigated. The pebbles were found to be very dissimilar with respect to their total tritium content—2.5–9 MBq g−1. The batch contained also some coarse agglomerates of the pebbles containing 10–19 MBq g−1 of tritium having also a high tritium release. For the pebbles having the total tritium 2.5–5.3 MBq g−1, the electron radiation for 3 h caused the fractional tritium release 17–26% (B = 0) and 21–29% (B = 1.7 T), the temperature …

Materials scienceMechanical EngineeringRadiochemistrychemistry.chemical_elementBlanketFusion powerNuclear physicsNuclear Energy and EngineeringchemistryAgglomerateGeneral Materials ScienceNeutronTritiumIrradiationBerylliumHeliumCivil and Structural EngineeringFusion Engineering and Design
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Radiation effects on stress evolution and dimensional stability of large fusion energy structures

2021

Abstract We assess the effects of neutron irradiation on the deformation and stress evolution of large-scale fusion energy structures. This is accomplished through non-linear finite element structural analysis of the coupled thermal and mechanical fields at the Beginning-Of-Life (BOL), at 45 dpa, and at 90 dpa. Radiation effects include volumetric swelling and the influence of radiation on the mechanical properties. The system studied here is a large section of a full inboard module of an integrated structure comprising the First Wall and Blanket (FW/B) of a Dual Cooled Lithium-Lead (DCLL) energy conversion unit in the Fusion Nuclear Science Facility (FNSF). The structural material is the f…

Materials scienceMechanical EngineeringStress–strain curveBlanketPlasticityFusion powerStress (mechanics)Nuclear Energy and EngineeringEnergy transformationNuclear fusionGeneral Materials ScienceDeformation (engineering)Composite materialCivil and Structural EngineeringFusion Engineering and Design
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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
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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
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A Comprehensive Model for the Auto-Ignition Prediction in Spark Ignition Engines Fueled With Mixtures of Gasoline and Methane-Based Fuel

2018

The introduction of natural gas (NG) in the road transport market is proceeding through bifuel vehicles, which, endowed of a double-injection system, can run either with gasoline or with NG. A third possibility is the simultaneous combustion of NG and gasoline, called double-fuel (DF) combustion: the addition of methane to gasoline allows to run the engine with stoichiometric air even at full load, without knocking phenomena, increasing engine efficiency of about 26% and cutting pollutant emissions by 90%. The introduction of DF combustion into series production vehicles requires, however, proper engine calibration (i.e., determination of DF injection and spark timing maps), a process which…

Materials scienceNuclear engineeringEnergy Engineering and Power TechnologyAerospace Engineeringknock modelingCombustionMethaneAuto ignitionlaw.inventionchemistry.chemical_compoundlawNatural gasSpark-ignition engineSpark (mathematics)Gasolinebusiness.industrymethaneMechanical Engineeringauto-ignitionnatural gaIgnition systemSettore ING-IND/08 - Macchine A FluidoFuel TechnologyNuclear Energy and Engineeringchemistryspark ignition enginebusinessJournal of Engineering for Gas Turbines and Power
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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
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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
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