Search results for "Nuclear engineering"

showing 10 items of 533 documents

On the impact of the heat transfer modelling approach on the prediction of EU-DEMO WCLL breeding blanket thermal performances

2020

Abstract The Water-Cooled Lithium-Lead Breeding Blanket is a key component of a fusion power plant, in charge of ensure Tritium production, shield Vacuum Vessel and magnets and remove the heat power deposited by radiation and particles arising from plasma. The last function is fulfilled by First Wall and Breeding Zone independent cooling systems. Several layouts of BZ coolant system have been investigated in the last years to identify a configuration that might guarantee EUROFER temperature below the limit (550 °C) and good thermal-hydraulic performances (i.e. water outlet temperature of 328 °C). A research activity is conducted to study and compare different modelling approaches to simulat…

ConvectionLiquid metalMaterials scienceNuclear engineeringBlanket engineeringBlanket7. Clean energy01 natural sciences010305 fluids & plasmasBreeder (animal)0103 physical sciencesGeneral Materials Science010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFEMFinite volume methodWCLL; CFD; FEM; breeding blanket; blanket engineeringMechanical EngineeringFinite element methodCoolantWCLLNuclear Energy and EngineeringHeat transferBreeding blanketCFD
researchProduct

Study of a water-cooled convective divertor prototype for the DEMO fusion reactor

2000

The plasma facing components of a fusion power reactor have a large impact on the overall plant design, its performance and availability and on the cost of electricity. The present work concerns a study of feasibility for a water-cooled prototype of the convective divertor component of the DEMO fusion reactor. The study has been carried out in two steps. In the first one thermal-hydraulic and neutronic parametric analyses have been performed to find out the prototype optimized configuration. In the second step thermo-mechanical analyses have been carried out on the obtained configuration to investigate the potential and limits of the proposed prototype, with a particular reference to the ma…

ConvectionNeutron transportMaterials scienceHeat fluxCritical heat fluxDivertorNuclear engineeringNUCLEAR FUSION DEMO REACTOR DIVERTOR THERMO-MECHANICSHeat transferMechanical engineeringNuclear fusionFusion powerAIP Conference Proceedings
researchProduct

Modeling of Melt Flow and Heat Transfer in Stationary Gas Tungsten Arc Welding with Vertical and Tilted Torches

2021

A 3D numerical simulation was conducted to study the transient development of temperature distribution in stationary gas tungsten arc welding with filler wire. Heat transfer to the filler wire and the workpiece was investigated with vertical (90°) and titled (70°) torches. Heat flux, current flux, and gas drag force were calculated from the steady-state simulation of the arc. The temperature in the filler wire was determined at three different time intervals: 0.12 s, 0.24 s, and 0.36 s. The filler wire was assumed not to deform during this short time, and was therefore simulated as solid. The temperature in the workpiece was calculated at the same intervals using heat flux, current flux, ga…

ConvectionTechnologyheat transfer to the filler wireMaterials scienceBuoyancytransient heat transfer in GTAWengineering.materialArticlelaw.inventionlawtilted torchGeneral Materials ScienceComposite materialMicroscopyQC120-168.85GTAW with filler wireMarangoni effectTorchGas tungsten arc weldingTQH201-278.5melt flow in weld poolgas tungsten arc weldingEngineering (General). Civil engineering (General)TK1-9971Volume (thermodynamics)Heat fluxDescriptive and experimental mechanicsHeat transferengineeringElectrical engineering. Electronics. Nuclear engineeringTA1-2040Materials
researchProduct

On the nuclear response of the helium-cooled lithium lead test blanket module in ITER

2005

Abstract The helium-cooled lithium lead (HCLL) concept has been recently selected as one of the two European reference designs foreseen for the breeding blanket of a demonstration fusion reactor. In particular, within the framework of the research and development activities on this blanket line, an HCLL test blanket module (TBM) has to be designed and manufactured to be implemented in ITER. At the Department of Nuclear Engineering (DIN) of the University of Palermo, a research campaign has been carried out to investigate the nuclear response of HCLL-TBM inside ITER by a numerical approach based on the Monte Carlo method. A realistic 3D heterogeneous model of HCLL-TBM has been set-up and ins…

CryostatMaterials scienceMechanical EngineeringNuclear engineeringMonte Carlo methodchemistry.chemical_elementBlanketFusion powerNuclear Energy and EngineeringchemistryTest blanket moduleHCLL-blanketNeutronicsRadiation damageNeutron sourceGeneral Materials ScienceLithiumSettore ING-IND/19 - Impianti NucleariHeliumCivil and Structural EngineeringFusion Engineering and Design
researchProduct

A study of the potential influence of frame coolant distribution on the radiation-induced damage of HCLL-TBM structural material

2008

Abstract Within the European Fusion Technology Programme, the Helium-Cooled Lithium Lead (HCLL) breeding blanket concept is one of the two EU lines to be developed for a Long Term fusion reactor, in particular with the aim of manufacturing a Test Blanket Module (TBM) to be implemented in ITER. The HCLL-TBM is foreseen to be located in an ITER equatorial port, being housed inside a steel-supporting frame, actively cooled by pressurized water. That supporting frame has been designed to house two different TBMs, providing two cavities separated by a dividing Plate 20 cm thick. As the nuclear response of HCLL-TBM might vary accordingly to the supporting frame configuration and composition, at t…

CryostatNeutron transportMaterials scienceMechanical EngineeringNuclear engineeringFrame (networking)Fusion powerBlanketCoolantNuclear Energy and EngineeringNeutron sourceGeneral Materials ScienceLithium-lead blanket TBM NeutronicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringParametric statisticsFusion Engineering and Design
researchProduct

Study of the helium-cooled lithium lead test blanket module nuclear behaviour under irradiation in ITER

2009

Abstract The present paper deals with the detailed investigation of the helium-cooled lithium lead test blanket module (HCLL-TBM) nuclear behaviour under irradiation in ITER, carried out at the Department of Nuclear Engineering of the University of Palermo adopting a numerical approach based on the Monte Carlo method. A realistic 3D heterogeneous model of the HCLL-TBM was set-up and inserted into an ITER 3D semi-heterogeneous model that realistically simulates the reactor lay-out up to the cryostat. A Gaussian-shaped neutron source was adopted for the calculations. The main features of the HCLL-TBM nuclear response were assessed, paying a particular attention to the neutronic and photonic d…

CryostatNeutron transportTokamakMaterials scienceMechanical EngineeringNuclear engineeringchemistry.chemical_elementFusion powerBlanketHCLL test blanket module Neutronics Monte Carlo methodlaw.inventionNuclear physicsNuclear Energy and EngineeringchemistrylawNeutron sourceGeneral Materials ScienceLithiumSettore ING-IND/19 - Impianti NucleariHeliumCivil and Structural EngineeringFusion Engineering and Design
researchProduct

Eurofusion-DEMO Divertor - Cassette Design and Integration

2020

International audience; The Eurofusion-DEMO design will complete the Pre Conceptual Design phase (PCD) with a PCD Gate, named G1, scheduled to take place in Q4 2020 that will focus on assessing the feasibility of the plant and its main components prior to entering into the Conceptual Design phase. In the paper first an overview is given of the Eurofusion-DEMO Divertor Assembly including design and interface description, systems and functional requirements, load specification, system classification, manufacturing procedures and cost estimate. Then critical issues are discussed and potential design solutions are proposed, e.g.:- Neutron material damage limits of the different (structural) mat…

DEMO; Divertor; CAD DesignMaterials sciencePassive coolingNuclear engineeringPort (circuit theory)01 natural sciences7. Clean energy010305 fluids & plasmas[SPI]Engineering Sciences [physics]DivertorConceptual design0103 physical sciencesDEMO fusion reactorGeneral Materials ScienceCAD Design010306 general physicsDEMOnuclear fusionSettore ING-IND/19 - Impianti NucleariCivil and Structural Engineeringelectromagnetic computationToroidNuclear heatingSeparatrixMechanical EngineeringDivertornuclear fusion plasma control electromagnetic computationNuclear Energy and EngineeringTUNGSTEN/EUROFER COATING SYSTEM CONCEPTUAL DESIGN COOLING CIRCUIT PROGRESS HCLLplasma controlHigh heat
researchProduct

The Histone Deacetylase Inhibitor JAHA Down-Regulates pERK and Global DNA Methylation in MDA-MB231 Breast Cancer Cells

2015

The histone deacetylase inhibitor N-1-(ferrocenyl)-N-8-hydroxyoctanediamide (JAHA) down-regulates extracellular-signal-regulated kinase (ERK) and its activated form in triple-negative MDA-MB231 breast cancer cells after 18 h and up to 30 h of treatment, and to a lesser extent AKT and phospho-AKT after 30 h and up to 48 h of treatment. Also, DNA methyltransferase 1 (DNMT1), 3b and, to a lesser extent, 3a, downstream ERK targets, were down-regulated already at 18 h with an increase up to 48 h of exposure. Methylation-sensitive restriction arbitrarily-primed (MeSAP) polymerase chain reaction (PCR) analysis confirmed the ability of JAHA to induce genome-wide DNA hypomethylation at 48 h of expos…

DNA methyltransferase (DNMT)medicine.drug_classDNA methyltransferaselcsh:TechnologymedicineGeneral Materials ScienceCancer epigeneticsSettore BIO/06 - Anatomia Comparata E Citologialcsh:Microscopyhistone deacetylase inhibitorlcsh:QC120-168.85QD0415Histone deacetylase 5lcsh:QH201-278.5extracellular-signal-regulated kinase (ERK)ChemistryHistone deacetylase 2lcsh:TCommunicationAKTHistone deacetylase inhibitorMolecular biologySettore BIO/18 - Geneticalcsh:TA1-2040DNA methylationDNMT1lcsh:Descriptive and experimental mechanicslcsh:Electrical engineering. Electronics. Nuclear engineeringlcsh:Engineering (General). Civil engineering (General)lcsh:TK1-9971DNA hypomethylationQD0241
researchProduct

Design, construction and cooling system performance of a prototype cryogenic stopping cell for the Super-FRS at FAIR

2015

A cryogenic stopping cell for stopping energetic radioactive ions and extracting them as a low energy beam was developed. This first ever cryogenically operated stopping cell serves as prototype device for the Low-Energy Branch of the Super-FRS at FAIR. The cell has a stopping volume that is 1 m long and 25 cm in diameter. Ions are guided by a DC field along the length of the stopping cell and by a combined RF and DC fields provided by an RE carpet at the exit-hole side. The ultra-high purity of the stopping gas required for optimum ion survival is reached by cryogenic operation. The design considerations and construction of the cryogenic stopping cell, as well as some performance character…

Dc fieldNuclear and High Energy PhysicsSPACE-CHARGEPhysics::Instrumentation and DetectorsNuclear engineering7. Clean energy01 natural sciencesIonNuclear physicsSuper-FRSENERGYCryogenic stopping cell0103 physical sciencesWater coolingddc:530FACILITYradioactive ion beams010306 general physicsInstrumentationRADIOACTIVE IONSFinal versionPhysicsCATCHERSPECTROSCOPYta114010308 nuclear & particles physicsCYCLOTRON GAS STOPPERCryocoolerSpace chargeVolume (thermodynamics)13. Climate actionIon catcherRadioactive on beamsFLIGHT MASS-SPECTROMETRYPROJECTILE FRAGMENTSBeam (structure)ION GUIDE
researchProduct

In Vitro Evaluation of the Biological Effects of ACTIVA Kids BioACTIVE Restorative, Ionolux, and Riva Light Cure on Human Dental Pulp Stem Cells

2019

This study aimed to analyze the biological effects of three new bioactive materials on cell survival, migration, morphology, and attachment in vitro. ACTIVA Kids BioACTIVE Restorative (Pulpdent, Watertown, MA, USA) (Activa), Ionolux (Voco, Cuxhaven, Germany), and Riva Light Cure UV (SDI, Bayswater, Australia) (Riva) were handled and conditioned with a serum-free culture medium. Stem cells from human dental pulp (hDPSCs) were exposed to material extracts, and metabolic activity, cell migration, and cell morphology were evaluated. Cell adhesion to the different materials was analyzed by scanning electron microscopy (SEM). The chemical composition of the materials was evaluated by energy-dispe…

Dental materialsCytotoxicityCellGlass ionomer cement02 engineering and technologyCell morphologylcsh:TechnologyOdontologiaArticleBiological properties03 medical and health sciences0302 clinical medicineDental pulp stem cellsdental pulp cellsmedicinedental materialsGeneral Materials ScienceViability assayBioactive materialslcsh:MicroscopyCell adhesionlcsh:QC120-168.85biological propertieslcsh:QH201-278.5lcsh:TChemistrybioactive materialsCell migration030206 dentistry021001 nanoscience & nanotechnologyMolecular biologyDental pulp cellsmedicine.anatomical_structurelcsh:TA1-2040cytotoxicitylcsh:Descriptive and experimental mechanicslcsh:Electrical engineering. Electronics. Nuclear engineeringStem celllcsh:Engineering (General). Civil engineering (General)0210 nano-technologylcsh:TK1-9971Materials
researchProduct