Search results for "PLASMA"

showing 10 items of 4043 documents

Preparation and characterization of sodium iron titanate ion exchanger and its application in heavy metal removal from waste waters.

2006

Abstract The ion exchange properties of sodium iron titanates, namely, NaFeTiO4, Na2Fe2Ti6O16 and iron-doped sodium nonatitanate were investigated. Conventional solid state and sol–gel methods were used in the synthesis of the sodium iron titanates. Structural characterization of the materials was performed with powder X-ray diffraction (XRD), thermogravimetry (TG), scanning electron microscopy (SEM) equipped with energy dispersive spectrometer (EDS) and with inductively coupled plasma optical emission spectrometry (ICP-OES). Based on TG analyses, the novel iron-doped sodium nonatitanate was proven to be a member of the layered titanate family. The different sodium iron titanates were compa…

TitaniumEnvironmental EngineeringAqueous solutionIon exchangeHealth Toxicology and MutagenesisSodiumPotassiumIronchemistry.chemical_elementIndustrial WasteOxidesPollutionTitanateThermogravimetryIon ExchangeNickelchemistryMetals HeavyEnvironmental ChemistryInductively coupled plasmaWaste Management and DisposalWater Pollutants ChemicalNuclear chemistryJournal of hazardous materials
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Digitizing data acquisition and time-of-flight pulse processing for ToF-ERDA

2016

A versatile system to capture and analyze signals from multi channel plate (MCP) based time-of-flight detectors and ionization based energy detectors such as silicon diodes and gas ionization chambers (GIC) is introduced. The system is based on commercial digitizers and custom software. It forms a part of a ToF-ERDA spectrometer, which has to be able to detect recoil atoms of many different species and energies. Compared to the currently used analogue electronics the digitizing system provides comparable time-of-flight resolution and improved hydrogen detection efficiency, while allowing the operation of the spectrometer be studied and optimized after the measurement. The hardware, data acq…

ToF-ERDANuclear and High Energy PhysicsMaterials sciencedata acquisitionPhysics::Instrumentation and DetectorsIon beam analysisAnalytical chemistrytime-of-flight01 natural sciences010305 fluids & plasmasdigitizerOpticsData acquisitionIonization0103 physical sciencesInstrumentationDiodeta114SpectrometerAnalogue electronics010308 nuclear & particles physicsbusiness.industryDetectorTime of flightCustom softwarebusinesstiedonhankinta
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Trajectory bending and energy spreading of charged ions in time-of-flight telescopes used for ion beam analysis

2014

Carbon foil time pick-up detectors are widely used in pairs in ion beam applications as time-of-flight detectors. These detectors are suitable for a wide energy range and for all ions but at the lowest energies the tandem effect limits the achievable time of flight and therefore the energy resolution. Tandem effect occurs when an ion passes the first carbon foil of the timing detector and its charge state is changed. As the carbon foil of the first timing detector has often a non-zero voltage the ion can accelerate or decelerate before and after the timing detector. The combination of different charge state properties before and after the carbon foil now induces spread to the measured times…

ToF-ERDANuclear and High Energy PhysicsRange (particle radiation)Ion beam analysista114Ion beamPhysics::Instrumentation and DetectorsChemistryDetectortandem effectIonTime of flightPhysics::Plasma Physicscarbon foilElectric fieldtime-of-flighToF-EAtomic physicsInstrumentationFOIL methodNuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms
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Development of helium coolant DEMO first wall model for SYCOMORE system code based on HCLL concept

2018

Abstract The conceptual design of the demonstration fusion power reactor, known as DEMO, is ongoing and several reactor configurations have to be investigated by exploring different design parameters. For these reasons, within the European framework, systems codes like SYCOMORE (SYstem COde for MOdelling tokamak REactor) have been developed. SYCOMORE includes several specific modules, one of which is aimed to define a suitable design of the helium breeding blanket. The research activity has been devoted to improve the method to define automatically the First Wall design starting from thermal-hydraulic and thermo-mechanical considerations, using analytical design formulae and, also, taking i…

TokamakComputer scienceNuclear engineeringBlanket7. Clean energy01 natural sciences010305 fluids & plasmaslaw.invention[SPI]Engineering Sciences [physics]Development (topology)Conceptual designlawSystem code0103 physical sciencesThermalGeneral Materials Science010306 general physicsDEMOCivil and Structural EngineeringFW HCLLMechanical EngineeringFusion powerFinite element methodNuclear Energy and EngineeringBreeding blanketGeometric modelingSYCOMORE
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Initial layout of DEMO buildings and configuration of the main plant systems

2018

Abstract The realization of a Demonstration Fusion Power Reactor (DEMO) to follow ITER, with the capability of generating several hundred MW of net electricity and operating with a closed fuel-cycle is viewed by Europe and many of the nations engaged in the construction of ITER as the remaining crucial step towards the exploitation of fusion power. The development of suitable configurations of plant systems inside the tokamak building to allow for the various maintenance operations and to meet the numerous system operating functions and safety requirements is one of the initial priorities. A task to establish an initial layout of the DEMO buildings and the integration of the main plant syst…

TokamakComputer sciencebusiness.industryMechanical EngineeringSeparation (aeronautics)Thermal power stationFusion powerNuclear power7. Clean energy01 natural sciences010305 fluids & plasmaslaw.inventionTask (project management)Nuclear Energy and Engineeringlaw0103 physical sciencesSystems engineeringGeneral Materials ScienceElectricity010306 general physicsbusinessZoningCivil and Structural EngineeringFusion Engineering and Design
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Status of ITER TBM port plug conceptual design and analyses

2014

The test blanket module port plug (TBM PP) consists of a TBM frame and two TBM-sets. However, at any time of the ITER operation, a TBM set can be replaced by a dummy TBM. The frame provides a standardized interface with the vacuum vessel (VV)/port structure and provides thermal isolation from the shield blanket. As one of the plasma-facing components, it shall withstand heat loads while at the same time provide adequate neutron shielding for the VV and magnet coils. The frame design shall provide a stable engineering solution to hold TBM-sets and also provide a mean for rapid remote handling replacement and refurbishment. This paper presents main design features of the conceptual design of …

TokamakITER Tokamak Plasma facing components TBM port plug (TBM PP)TokamakComputer scienceMechanical EngineeringInterface (computing)Nuclear engineeringFrame (networking)Port (circuit theory)BlanketPlasma facing componentlaw.inventionNuclear Energy and EngineeringConceptual designlawITERShieldElectromagnetic shieldingGeneral Materials ScienceTBM port plug (TBM PP)Settore ING-IND/19 - Impianti NucleariTokamak;TBM port plug (TBM PP);Plasma facing components;ITERPlasma facing componentsCivil and Structural EngineeringFusion Engineering and Design
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Conceptual Design and Modeling of Fast Discharge Unit for Quench Protection of Superconducting Toroidal Field Magnets of DTT

2020

The paper deals with the modelling and simulation of a Fast Discharge Unit (FDU) for quench protection of the Toroidal Field (TF) magnets of the Divertor Tokamak Test, an experimental facility under design and construction in Frascati (Italy). The FDU is a safety key component that protects the superconducting magnets when a quench is detected through the fast extraction of the energy stored in superconducting magnets by adding in the TF magnets a dump (or discharge) resistor. In the paper, two different configurations of dump resistors (fixed and variable respectively) have been analysed and discussed. As a first result, it is possible to underline that the configuration with variable dump…

TokamakMaterials scienceNuclear engineeringFDUSuperconducting magnet01 natural sciences010305 fluids & plasmaslaw.inventionhybrid circuit breakerConceptual designPhysics::Plasma Physicslaw0103 physical sciencesdump resisto010306 general physicsSuperconductivityToroidal fieldDivertorquench protectionSettore ING-IND/33 - Sistemi Elettrici Per L'EnergiaSettore ING-IND/31 - ElettrotecnicaMagnetPhysics::Accelerator Physicssuperconducting magnetsResistorQPC2020 IEEE 20th Mediterranean Electrotechnical Conference ( MELECON)
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Confirmation of the topology of the Wendelstein 7-X magnetic field to better than 1:100,000

2016

Fusion energy research has in the past 40 years focused primarily on the tokamak concept, but recent advances in plasma theory and computational power have led to renewed interest in stellarators. The largest and most sophisticated stellarator in the world, Wendelstein 7-X (W7-X), has just started operation, with the aim to show that the earlier weaknesses of this concept have been addressed successfully, and that the intrinsic advantages of the concept persist, also at plasma parameters approaching those of a future fusion power plant. Here we show the first physics results, obtained before plasma operation: that the carefully tailored topology of nested magnetic surfaces needed for good c…

TokamakPlasma parametersScienceGeneral Physics and AstronomyTopology (electrical circuits)Topology7. Clean energy01 natural sciencesArticleGeneral Biochemistry Genetics and Molecular Biology010305 fluids & plasmaslaw.inventionlaw0103 physical sciences010306 general physicsPhysicsFusion Wendelstein7-X StellaratorMultidisciplinaryta114QGeneral ChemistryPlasmaFusion powerMagnetic fieldErratumWendelstein 7-XStellarator
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Modelling of combined ICRF and NBI heating in JET hybrid plasmas

2017

During the 2015-2016 JET campaigns many efforts have been devoted to the exploration of high performance plasma scenarios envisaged for ITER operation. In this paper we model the combined ICRF+NBI heating in selected key hybrid discharges using PION. The antenna frequency was tuned to match the cyclotron frequency of minority hydrogen (H) at the center of the tokamak coinciding with the second harmonic cyclotron resonance of deuterium. The modelling takes into account the synergy between ICRF and NBI heating through the second harmonic cyclotron resonance of deuterium beam ions which allows us to assess its impact on the neutron rate RNT. We evaluate the influence of H concentration which w…

TokamakQC1-999CyclotronCyclotron resonance01 natural sciences7. Clean energyFusió nuclear controlada010305 fluids & plasmaslaw.inventionlawNBI heating0103 physical sciencesNeutron010306 general physicsFusion reactionsICRF and NBI heatingJet (fluid)ICRF:Física [Àrees temàtiques de la UPC]ChemistryPhysicsPlasmaFusion powerComputational physicsJET hybrid plasmasHarmonicAtomic physicsEPJ Web of Conferences
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The Role of Combined ICRF and NBI Heating in JET Hybrid Plasmas in Quest for High D-T Fusion Yield

2017

Combined ICRF and NBI heating played a key role in achieving the world-record fusion yield in the first deuterium-tritium campaign at the JET tokamak in 1997. The current plans for JET include new experiments with deuterium-tritium (D-T) plasmas with more ITER-like conditions given the recently installed ITER-like wall (ILW). In the 2015-2016 campaigns, significant efforts have been devoted to the development of high-performance plasma scenarios compatible with ILW in preparation of the forthcoming D-T campaign. Good progress was made in both the inductive (baseline) and the hybrid scenario: a new record JET ILW fusion yield with a significantly extended duration of the high-performance pha…

TokamakQC1-999Nuclear engineering7. Clean energy01 natural sciencesFusió nuclear controlada010305 fluids & plasmasPlasma currentlaw.inventionlawNBI heating0103 physical sciencesNeutron010306 general physicsFusionFusion reactionsHigh D-T Fusion YieldPhysicsFusionJet (fluid):Física [Àrees temàtiques de la UPC]ICRFbusiness.industryPhysicsElectrical engineeringPlasmaYield (chemistry)Beta (plasma physics)JET Hybrid PlasmasNBI Heatingbusiness
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