Search results for "Nuclear engineering"

showing 10 items of 533 documents

EP-1168: RapidArc independent monitor unit calculations with Diamond. Practical considerations

2013

Monitor unitMaterials scienceOncologyRadiology Nuclear Medicine and imagingNuclear engineeringengineeringDiamondRadiology Nuclear Medicine and imagingHematologyengineering.materialRadiotherapy and Oncology
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Investigation of hydrogen and deuterium impact on the release of tritium from two-phase lithium ceramics under reactor irradiation

2022

In the development of fusion energy, an important task is the study and improvement of tritium production technologies. In this case, one of the most promising materials for tritium generation is lithium ceramics. Considering the importance of the task, numerous studies are aimed at solving the problem of determining the parameters and mechanisms of tritium release in lithium-containing materials. This paper presents the results of a study of tritium release processes from two-phase lithium ceramics of Li$_{4}$SiO$_{4}$/Li$_{2}$TiO$_{3}$ during reactor irradiation when hydrogen and deuterium are injected into the chamber with irradiated samples. The mechanisms regularities of the tritium yi…

Neutron irradiationTechnologyTritium releaseNuclear and High Energy PhysicsNuclear Energy and EngineeringMaterials Science (miscellaneous)TK9001-9401Nuclear engineering. Atomic powerTritiumDeuteriumddc:600Two-phase lithium ceramicNuclear Materials and Energy
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A neutron point kinetic model for fusion relevant calculations

2012

Abstract In the framework of research activities on fusion reactors a great effort is dedicated by the scientific community to the development of tritium breeding blankets. One of the main goals is to assess the neutronic behaviour of such devices to analyse their tritium breeding performance and to evaluate the required data for their thermal–mechanic and thermal–hydraulic design. Many papers have been published on this topic considering some stationary condition to calculate such important quantities as heating power, gas production and dpa rates, tritium breeding ratio, etc., but not much attention has been focussed to neutronic transport analyses in transient conditions. The present pap…

Neutron transportComputer scienceMechanical EngineeringNuclear engineeringNumerical analysisMonte Carlo methodNeutron kinetic Blanket HCLL-TBMBlanketFusion powerNuclear physicsNuclear Energy and EngineeringGeneral Materials SciencePoint (geometry)NeutronTransient (oscillation)Settore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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Automated parametric neutronics analysis of the Helium Cooled Pebble Bed breeder blanket with Be 12 Ti

2017

The Helium Cooled Pebble Bed (HCPB) breeder blanket is being developed as part of the European Fusion Programme. Part of the programme is to investigate blanket designs relevant for future demonstration fusion power plants. This paper presents neutronics analyses of the HCPB with an alternative neutron multiplier, Be12Ti which is incorporated into the design, replacing the current Be multiplier. A parameter study was performed for a range of geometries to identify the optimal heights of the lithium ceramic and neutron multiplier pebble beds. Automated creation of CAD models followed by conversion to constructive solid geometry (CSG) and unstructured mesh (UM) geometry allows the models to b…

Neutron transportMaterials scienceNuclear engineeringHCPBNeutronicBlanket01 natural sciences7. Clean energy010305 fluids & plasmasBreeder blanketConstructive solid geometryMaterials Science(all)0103 physical sciencesGeneral Materials ScienceNeutronCAD010306 general physicsPebbleFusionParametricSettore ING-IND/19 - Impianti NucleariParametric statisticsCivil and Structural EngineeringMechanical EngineeringFusion powerNuclear Energy and EngineeringMultiplier (economics)CoupledVolumetric heatingFusion Engineering and Design
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Investigation of the DEMO WCLL Breeding Blanket Cooling Water Activation

2020

Abstract Within the framework of the activities foreseen by the EUROfusion action on the cooling water activation assessment for a DEMO reactor equipped with a Water Cooled Lithium Lead Breeding Blanket (WCLL BB), the University of Palermo is involved in the assessment of dose rates induced by the decay of nitrogen radioisotopes produced by water activation, nearby the main components (e.g. isolation valves) of both First Wall (FW) and Breeder Zone (BZ) cooling circuits. In particular, the aim of this work is to evaluate the spatial distribution of nitrogen isotopes (16N and 17N) in the WCLL BB cooling circuits. To this purpose, a coupled neutronic/fluid-dynamic problem is solved following …

Neutron transportMechanical EngineeringNuclear engineeringFlow (psychology)Isolation valveDEMO reactorBlanket01 natural sciences010305 fluids & plasmas010101 applied mathematicsNitrogen RadioisotopesBreeder (animal)Nuclear Energy and Engineering0103 physical sciencesHeat transferWater coolingNeutronicsEnvironmental scienceGeneral Materials ScienceWCLL BlanketFluid-dynamics0101 mathematicsSettore ING-IND/19 - Impianti NucleariCivil and Structural Engineering
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Computational thermofluid-dynamic analysis of DEMO divertor cassette body cooling circuit

2018

Abstract Within the framework of the Work Package Divertor, Subproject: Cassette Design and Integration (WPDIV-Cassette) 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. 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. Fully-coupled fluid-structure CFD analyses have been carried out for the recently-revised cassette body cooling circuit under nominal steady state conditions, imposing a non-uniform sp…

Neutron transportNuclear engineeringComputational fluid dynamicsThermofluid-dynamic01 natural sciences010305 fluids & plasmasDivertor0103 physical sciencesWater coolingGeneral Materials ScienceTotal pressureCFD analysi010306 general physicsDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFinite volume methodSteady stateCassette bodybusiness.industryDivertorMechanical EngineeringCoolantNuclear Energy and EngineeringEnvironmental scienceMaterials Science (all)business
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Nuclear performances of the water-cooled lithium lead DEMO reactor: Neutronic analysis on a fully heterogeneous model

2021

Abstract The development of a conceptual design for the Demonstration Fusion Power Reactor (DEMO) is a key issue within the EUROfusion roadmap. The DEMO reactor is designed to produce a fusion power of about 2 GW and generate a substantial amount of electricity, relying on a closed tritium fuel cycle: it implies that the breeding blanket (BB) shall guarantee a suitable tritium production to enable a continuous operation without any external supply. The Water-Cooled Lithium Lead (WCLL) concept is a candidate for the DEMO BB: it uses liquid Lithium Lead as breeder and neutron multiplier and water in PWR condition as coolant. The neutronics analyses carried out in the past have been performed …

Neutron transportTokamakBreeding blanket;Computer scienceNuclear engineeringBlanket01 natural sciences010305 fluids & plasmaslaw.inventionBreeder (animal)Conceptual designlaw0103 physical sciencesMCNPNeutronicsGeneral Materials ScienceNeutron010306 general physicsDEMOCivil and Structural EngineeringMechanical EngineeringFusion powerWCLLCoolantNuclear Energy and EngineeringNuclear analysisBreeding blanketFusion Engineering and Design
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Radiative neutron capture on 242Pu in the resonance region at the CERN n_TOF-EAR1 facility

2018

The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined with uranium to make mixed oxide (MOX) fuel. In this way the Pu from spent fuel is used in a new reactor cycle, contributing to the long-term sustainability of nuclear energy. However, an extensive use of MOX fuels, in particular in fast reactors, requires more accurate capture and fission cross sections for some Pu isotopes. In the case of 242Pu there are sizable discrepancies among the existing capture cross-section measurements included in the evaluations (all from the 1970s) resulting in an uncertainty as high as 35% in the fast energy region. Moreover, post-irradiation experiments evalua…

NeutronsSpent nuclear fuel:Energies::Energia nuclear [Àrees temàtiques de la UPC]Nuclear engineeringCross sectionnTOF:Física [Àrees temàtiques de la UPC]Enginyeria nuclearNuclear fuelNEACERNNeutron
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A Comparative Analysis of Residual Block Alternatives for End-to-End Audio Classification

2020

Residual learning is known for being a learning framework that facilitates the training of very deep neural networks. Residual blocks or units are made up of a set of stacked layers, where the inputs are added back to their outputs with the aim of creating identity mappings. In practice, such identity mappings are accomplished by means of the so-called skip or shortcut connections. However, multiple implementation alternatives arise with respect to where such skip connections are applied within the set of stacked layers making up a residual block. While residual networks for image classification using convolutional neural networks (CNNs) have been widely discussed in the literature, their a…

Normalization (statistics)General Computer ScienceComputer scienceFeature extractionESC02 engineering and technologycomputer.software_genreResidualConvolutional neural networkconvolutional neural networks0202 electrical engineering electronic engineering information engineeringGeneral Materials Scienceurbansound8kAudio signal processingBlock (data storage)Contextual image classificationGeneral EngineeringAudio classification020206 networking & telecommunications113 Computer and information sciences020201 artificial intelligence & image processinglcsh:Electrical engineering. Electronics. Nuclear engineeringData mininglcsh:TK1-9971computerresidual learningIEEE Access
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Analysis, by RELAP5 code, of Boron Dilution Phenomena in Small Break LOCA and in Mid Loop Operation Transients, Performed in PKL III Test Facility

2008

Nuclear Engineering Thermal HydraulicSettore ING-IND/19 - Impianti Nucleari
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