Search results for " reactor"

showing 10 items of 361 documents

Comparison of different predictive models for nutrient estimation in a sequencing batch reactor for wastewater treatment

2006

Abstract In this paper different predictive models for nutrient estimation in a sequencing batch reactor (SBR) for wastewater treatment are compared: principal component regression (PCR), partial least squares (PLS), and artificial neural networks (ANNs). Two unfolding procedures were used: batch-wise and variable-wise. For the latter unfolding method, X and Y matrix augmentation with lagged variables were used in some models to incorporate process dynamics. The results have shown that batch-wise unfolding PLS models outperform the other approaches. The ANN models are good predictive models, but in this particular case-study, they do not outperform those multivariate projection models that …

Multivariate statisticsArtificial neural networkbusiness.industryComputer scienceProcess Chemistry and TechnologySequencing batch reactorSoft sensorMachine learningcomputer.software_genreMissing dataComputer Science ApplicationsAnalytical ChemistryPartial least squares regressionPrincipal component regressionArtificial intelligenceData miningbusinesscomputerModel buildingSpectroscopySoftwareChemometrics and Intelligent Laboratory Systems
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Multivariate SPC of a sequencing batch reactor for wastewater treatment

2007

Data from a sequencing batch reactor (SBR) operated for enhanced biological phosphorus removal from wastewater have been analysed in order to propose an efficient MSPC scheme of the process. Different multivariate bilinear approaches have been applied and compared in terms of their capabilities for on-line and off-line fault detection and diagnosis. The typical three-way data structure from a batch process was unfolded batch-wise and variable-wise. In the latter case, two models were built: with (AT) and without (WKFH) removing the main non-linear behaviour of the process data. Since the process consists of several stages, the monitoring strategies tested include: one model for all stages a…

Multivariate statisticsComputer sciencebusiness.industryProcess Chemistry and TechnologyProcess (computing)Bilinear interpolationSequencing batch reactorCovarianceData structureFault detection and isolationComputer Science ApplicationsAnalytical ChemistryBatch processingProcess engineeringbusinessSpectroscopySoftwareChemometrics and Intelligent Laboratory Systems
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WCLL breeding blanket design and integration for DEMO 2015: status and perspectives

2017

Abstract Water-cooled lithium-lead breeding blanket is considered a candidate option for European DEMO nuclear fusion reactor. ENEA and the linked third parties have proposed and are developing a multi-module blanket segment concept based on DEMO 2015 specifications. The layout of the module is based on horizontal (i.e. radial-toroidal) water-cooling tubes in the breeding zone, and on lithium lead flowing in radial-poloidal direction. This design choice is driven by the rationale to have a modular design, where a basic geometry is repeated along the poloidal direction. The modules are connected with a back supporting structure, designed to withstand thermal and mechanical loads due to norma…

Neutron transportComputer scienceBlanket7. Clean energy01 natural sciencesbreeding blanket; CFD; DEMO; WCLL010305 fluids & plasmaslaw.inventionlaw0103 physical sciencesDesign choiceGeneral Materials Science010306 general physicsWCLL Breeding blanket DEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringWCLL Breeding blanket DEMObusiness.industryMechanical EngineeringLead systemPressurized water reactorFusion powerModular designNuclear Energy and EngineeringSystems engineeringbusinessTransport systemFusion 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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On the thermal dynamic behaviour of the helium-cooled DEMO fusion reactor

2019

Abstract The EU-DEMO conceptual design is being conducted among research institutions and universities from 26 countries of European Union, Switzerland and Ukraine. Its mission is to realise electricity from nuclear fusion reaction by 2050. As DEMO has been conceived to deliver net electricity to the grid, the choice of the Breeding Blanket (BB) coolant plays a pivotal role in the reactor design having a strong influence on plant operation, safety and maintenance. In particular, due to the pulsed nature of the heat source, the Primary Heat Transfer System (PHTS) becomes a very important actor of the Balance of Plant (BoP) together with the Power Conversion System (PCS). Moreover, aiming to …

Nuclear Fusion DEMO reactor Blanket PHTSHistoryComputer science020209 energyNuclear engineering02 engineering and technologyBlanket01 natural sciences7. Clean energyEnergy storage010305 fluids & plasmasEducationConceptual design0103 physical sciences0202 electrical engineering electronic engineering information engineeringmedia_common.cataloged_instanceEuropean unionSettore ING-IND/19 - Impianti Nuclearimedia_commonbusiness.industryFusion powerComputer Science ApplicationsCoolantHeat transferElectricitybusinessJournal of Physics: Conference Series
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First-forbidden transitions in the reactor anomaly

2018

We study the dominant forbidden transitions in the antineutrino spectra of the fission actinides from 4 MeV onward using the nuclear shell model. Through explicit calculation of the shape factor, taking into account Coulomb corrections, we show the expected changes on cumulative electron and antineutrino spectra. Compared to the usual allowed approximation this results in a minor decrease of electron spectra from 4 MeV and onward, whereas an increase of several percent is observed in antineutrino spectra. We show that, despite their limited number, forbidden transitions dominate the spectral flux for most of the experimentally accessible range. Based on the shell model calculations we attem…

Nuclear TheoryMonte Carlo methodAb initioFOS: Physical sciencesElectronhiukkasfysiikka7. Clean energy01 natural sciencesSpectral lineHigh Energy Physics - ExperimentNuclear Theory (nucl-th)High Energy Physics - Experiment (hep-ex)0103 physical sciencesCoulombfissionNuclear Experiment (nucl-ex)Nuclear Experiment010306 general physicsNuclear ExperimentPhysics010308 nuclear & particles physicsneutrino interactionsshell modelNuclear shell modelComputational physicselectroweak interactions in nuclear physicsnuclear reactorsbeta decayAnomaly (physics)ydinfysiikkaParametrization
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Sensitivity Analysis of the MASLWR Helical Coil Steam Generator Using TRACE

2011

Accurate simulation of transient system behavior of a nuclear power plant is the goal of systems code calculations, and the evaluation of a code's calculation accuracy is accomplished by assessment and validation against appropriate system data. These system data may be developed either from a running system prototype or from a scaled model test facility, and characterize the thermal hydraulic phenomena during both steady state and transient conditions. The identification and characterization of the relevant thermal hydraulic phenomena, and the assessment and validation of thermal hydraulic systems codes, has been the objective of multiple international research programs. The validation and…

Nuclear and High Energy PhysicsEngineeringbusiness.industryMechanical EngineeringSuperheated steamNuclear engineeringNuclear Engineering Thermal HydraulicBoiler (power generation)System safetyNuclear reactorlaw.inventionThermal hydraulicsNatural circulationNuclear Energy and EngineeringNuclear reactor corelawHeat exchangerForensic engineeringGeneral Materials ScienceSafety Risk Reliability and QualitybusinessWaste Management and DisposalSettore ING-IND/19 - Impianti NucleariTRACE Code MASLWR SMR Helical Coils Steam Generator Natural Circulation
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Implementation of an aerodynamic lens for TRIGA-SPEC

2016

Abstract We report on the optimization of the gas-jet system employed to couple the TRIGA-SPEC experiment to the research reactor TRIGA Mainz. CdI2 aerosol particles suspended in N2 as carrier gas are used for an effective transport of fission products from neutron induced 235 U fission from the target chamber to a surface ion source. Operating conditions of the gas-jet were modified to enable the implementation of an aerodynamic lens, fitting into the limited space available in front of the ion source. The lens boosts the gas-jet efficiency by a factor of 4–10. The characterization of the gas-jet system as well as the design of the aerodynamic lens and efficiency studies are presented and …

Nuclear and High Energy PhysicsFission products010504 meteorology & atmospheric sciencesChemistrybusiness.industryFissionNuclear engineeringAerodynamics010403 inorganic & nuclear chemistry01 natural sciencesIon source0104 chemical sciencesTRIGAlaw.inventionLens (optics)OpticslawResearch reactorNeutronbusinessInstrumentation0105 earth and related environmental sciencesNuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms
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Very high specific activity erbium 169Er production for potential receptor-targeted radiotherapy

2019

Erbium 169Er is one of the most interesting radiolanthanides for new potential receptor-targeted β− therapy applications due to its low energy β− emissions, very low intensity ɣ rays and the possibility to use 68Ga or 44Sc as companion for diagnostic in a theranostics approach. Currently it can be produced in reactors through the neutron activation of highly enriched 168Er. The low specific activity of the produced carrier-added 169Er is limiting its use for receptor-targeted therapy. Nonetheless it is used for radiosynoviorthesis of small joints. The aim of this work is to develop a new large-scale production method for the supply of very high specific activity 169Er. Highly enriched 168Er…

Nuclear and High Energy PhysicsHIGH SPECIFIC ACTIVITIESMaterials scienceTargeted Radiotherapychemistry.chemical_elementLASER IONIZATION7. Clean energy030218 nuclear medicine & medical imaginglaw.inventionErbium03 medical and health sciences0302 clinical medicinePRECLINICAL STUDIESlaw[PHYS.HEXP]Physics [physics]/High Energy Physics - Experiment [hep-ex]Production (economics)HIGH SPECIFIC ACTIVITYIrradiationInstrumentationComputingMilieux_MISCELLANEOUSATOM LASERSRadiochemistrySELECTIVE IONIZATIONNuclear reactorERBIUMRESONANT LASER IONIZATIONLARGE SCALE PRODUCTIONSchemistryHigh specific activityER-169030220 oncology & carcinogenesisSEPARATION EFFICIENCYTARGETED RADIOTHERAPYIONIZATIONSpecific activityRECEPTOR-TARGETED THERAPYNeutron activationNUCLEAR REACTORSNuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms
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Thermo-mechanical testing of Li-ceramic for the helium cooled pebble bed (HCPB) breeding blanket

2004

The helium cooled pebble bed (HCPB) Test blanket module (TBM) for the DEMO Reactor foresees the utilization of lithiate ceramics as breeder in form of pebble beds. The pebbles are organized in several layers alternatively stacked among couples of cooling plates (CP). ENEA has launched an experimental programme for the out-of-pile thermo-mechanical testing of mock-ups simulating a portion of the HCPB-TBM. The programme foresees the fabrication and testing of different mock-ups, to be tested in the HE-FUS3 facility at ENEA Brasimone. The paper describes the HELICHETTA III campaign carried-out in 2003. In particular, the test section layout, the pebble filling procedure, the experimental set-u…

Nuclear and High Energy PhysicsMaterials scienceNuclear engineeringFUSION REACTOR BREEDING BLANKET PEBBLE BEDSchemistry.chemical_elementBlanketNuclear physicsBreeder (animal)Nuclear Energy and Engineeringchemistryvisual_artvisual_art.visual_art_mediumGeneral Materials ScienceCeramicPebbleHeliumThermo mechanicalSettore ING-IND/19 - Impianti Nucleari
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