Search results for "IMPIANTI"

showing 10 items of 797 documents

Fuzzy modelling of HEART methodology: application in safety analyses of accidental exposure in irradiation plants

2009

The present paper refers to the obtained results by using Fuzzy Fault Tree analyses of accidental scenarios which entail the potential exposure of operators working in irradiation industrial plants. For these analyses the HEART methodology, a first generation of the Human Reliability Analysis method, has been employed to evaluate the probability of human erroneous actions. This technique has been modified by us on the basis of fuzzy set concept to more directly take into account the uncertainties of the so called error-promoting factors, on which the method is grounded. The results allow also to provide some recommendations on procedures and safety equipments to reduce the radiological expo…

Nuclear and High Energy PhysicsRisk analyses Irradiation plant Human error Fuzzy Fault Tree.RadiationBasis (linear algebra)Settore ING-IND/20 - Misure E Strumentazione NucleariComputer scienceHuman errorFuzzy setCondensed Matter PhysicsFuzzy fault treeReliability engineeringAccidental exposureFuzzy modellingSafety EquipmentGeneral Materials ScienceSettore ING-IND/19 - Impianti NucleariHuman reliabilityRadiation Effects and Defects in Solids
researchProduct

On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material

2007

Within the European Fusion Technology Programme, research activities have been conducted on the Helium-Cooled Lithium Lead (HCLL) breeding blanket concept with the aim of manufacturing a Test Blanket Module (TBM) to be irradiated in ITER. HCLL-TBM is planned to be located in an ITER equatorial port, housed inside an AISI 316 stainless steel-supporting frame. Since that frame has been designed to provide two positions separated by a dividing plate and the HCLL-TBM is expected to fill one of them, its nuclear response could vary depending on the filling status of the other position and on the plate thickness. A parametric study has been carried out to investigate the potential effects on the …

Nuclear and High Energy PhysicsStructural materialMaterials scienceNuclear engineeringRadiation inducedBlanketFusion powerlaw.inventionNuclear Energy and EngineeringlawGeneral Materials ScienceTEST BLANKET MODULE NUCLEAR RESPONSE ITERSpark plugSettore ING-IND/19 - Impianti NucleariNuclear chemistry
researchProduct

Hydraulic analysis of EU-DEMO divertor plasma facing components cooling circuit under nominal operating scenarios

2019

Within 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 behaviour of the DEMO divertor cassette cooling circuit, focussing the attention on its Plasma Facing Components (PFCs). The research campaign has been carried out following a theoretical-computational approach based on the Finite Volume Method and adopting the commercial Computational Fluid-Dynamic code ANSYS-CFX. A realistic model of the PFCs cooling circuit has been analysed, specifically embedding each Plasma Facing Unit (PFU) cooling chann…

Nuclear engineeringCFD analysis; DEMO; Divertor; Plasma facing components; Thermofluid-dynamics7. Clean energy01 natural sciences010305 fluids & plasmasDivertor0103 physical sciencesGeneral Materials ScienceBoundary value problemCFD analysiTotal pressure010306 general physicsDEMOSettore ING-IND/19 - Impianti NucleariPlasma facing componentsCivil and Structural EngineeringThermofluid-dynamicsFinite volume methodSteady stateTurbulenceMechanical EngineeringDivertorPlasma facing componentCoolantVibrationNuclear Energy and EngineeringEnvironmental scienceCFD analysisFusion Engineering and Design
researchProduct

Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System

2021

Abstract The Water Cooled Lithium Lead Test Blanket System (WCLL TBS) is one of the EU Test Blanket Systems candidate for being installed and operated in ITER. In view of its Conceptual Design Review by F4E and ITER Organization (IO), planned for mid-September 2020, several technical activities have been performed in the areas of WCLL TBS Ancillary Systems design. In this article the outcomes of the conceptual design phase of the four main Ancillary Systems of WCLL TBS, namely the Water Cooling System (WCS), the Coolant Purification System (CPS), the PbLi loop and the Tritium Extraction System (TES), are reported and critically discussed. In particular, for each Ancillary System hereafter a…

Nuclear engineeringCPS; ITER; PbLi loop; TES; WCLL TBS; WCSchemistry.chemical_elementPbLi loopBlanket01 natural sciences010305 fluids & plasmasConceptual designITER0103 physical sciencesWater coolingGeneral Materials Science010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringMechanical EngineeringWater cooledCoolantNuclear Energy and EngineeringchemistryEnvironmental scienceSystems designLithiumCPSWCSTESWCLL TBS
researchProduct

On the numerical assessment of the thermal-hydraulic operating map of the DEMO Divertor Plasma Facing Components cooling circuit

2020

Abstract Within 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 thermal-hydraulic behaviour of the DEMO divertor cassette cooling system, focussing the attention on the 2018 configuration of the Plasma Facing Components (PFCs) circuit consistent with the DEMO baseline 2017. The research campaign has been carried out following a theoretical-computational approach based on the finite volume method and adopting the commercial Computational Fluid-Dynamic (CFD) code ANSYS CFX. A steady-state CFD analysis has been carried out for the …

Nuclear engineeringComputational fluid dynamics01 natural sciences010305 fluids & plasmasThermal hydraulicsDivertor0103 physical sciencesMass flow rateWater coolingGeneral Materials ScienceTotal pressure010306 general physicsDEMOPlasma facing componentsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringThermofluid-dynamicsCritical heat fluxbusiness.industryMechanical EngineeringDivertorCoolantNuclear Energy and EngineeringEnvironmental sciencebusinessCFD analysisFusion Engineering and Design
researchProduct

On the thermal-hydraulic optimization of DEMO divertor plasma facing components 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. Attention has been focussed on the divertor Plasma Facing Components (PFCs) cooling circuit and a parametric analysis has been carried out in order to assess the potential impact of proper layout changes on its thermal-hydraulic performances, mainly in terms of coolant total pressure drop, flow velocity distribution and margin against critical heat flux occurrence. The r…

Nuclear engineeringComputational fluid dynamicsThermofluid-dynamic01 natural sciences7. Clean energy010305 fluids & plasmasThermal hydraulicsDivertor0103 physical sciencesWater coolingGeneral Materials ScienceCFD analysi010306 general physicsDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFinite volume methodCritical heat fluxbusiness.industryDivertorMechanical EngineeringPlasma facing componentCoolantFlow velocityNuclear Energy and EngineeringEnvironmental scienceMaterials Science (all)businessFusion Engineering and Design
researchProduct

Hydraulic assessment of an upgraded pipework arrangement for the DEMO divertor plasma facing components cooling circuit

2021

Abstract In the context of the Work Package DIVertor (WPDIV) of the EUROfusion action, a research campaign has been carried out by University of Palermo in cooperation with ENEA to assess the thermal-hydraulic performances of the DEMO divertor cooling system, concentrating the attention on its 2019 Plasma Facing Components (PFCs) configuration, relevant to DEMO baseline 2017. The research activity has been performed following a theoretical-numerical technique based on the finite volume method and adopting the well-known ANSYS CFX CFD code. The PFCs cooling circuit thermal-hydraulic performances under nominal steady-state conditions, assessed mainly in terms of coolant total pressure drop, c…

Nuclear engineeringContext (language use)01 natural sciences010305 fluids & plasmaslaw.inventionDivertorlaw0103 physical sciencesWater coolingGeneral Materials ScienceTotal pressure010306 general physicsDEMOPlasma facing componentsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringThermofluid-dynamicsCritical heat fluxMechanical EngineeringDivertorCoolantAxial compressorNuclear Energy and EngineeringEnvironmental scienceInlet manifoldCFD analysis
researchProduct

Preliminary design of the top cap of DEMO Water-Cooled Lithium Lead breeding blanket segments

2020

Abstract Within the framework of EUROfusion R&D activity, a research campaign has been carried out at the University of Palermo, in close cooperation with ENEA labs, in order to preliminary design the top cap foreseen for the DEMO Water-Cooled Lithium Lead (WCLL) breeding blanket segments. Due to the high heat and pressure loads acting on such component, its design results particularly demanding and a specific multi-physics approach is needed, covering several aspects from thermal-hydraulics to structural assessments. Preliminary detailed CAD model of the cap integrated into the upper region of the WCLL breeding blanket outboard central segment has been set-up, equipped with proper cooling …

Nuclear engineeringchemistry.chemical_elementBlanket7. Clean energy01 natural sciencesTop cap010305 fluids & plasmasLead (geology)Component (UML)0103 physical sciencesGeneral Materials Science010306 general physicsDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringElectronic circuitStructural materialMechanical EngineeringWater cooledCapWCLLNuclear Energy and EngineeringchemistryEnvironmental scienceMulti-physicsLithiumBreeding blanketFusion Engineering and Design
researchProduct

Service quality benchmarking via a novel approach based on fuzzy ELECTRE III and IPA: an empirical case involving the Italian public healthcare conte…

2017

A novel fuzzy-based approach which combines ELECTRE III along with the Importance-Performance Analysis (IPA) is proposed in the present work to comparatively evaluate the service quality in the public healthcare context. Specifically, ELECTRE III is firstly considered to compare the service performance of examined hospitals in a noncompensatory manner. Afterwards, IPA is employed to support the service quality management to point out improvement needs and their priorities. The proposed approach also incorporates features of the Fuzzy Set Theory so as to address the possible uncertainty, subjectivity and vagueness of involved experts in evaluating the service quality. The model is applied to…

Operations researchQuality Assurance Health CareComputer scienceFuzzy setMedicine (miscellaneous)Context (language use)Service quality managementFuzzy logicHealth administration03 medical and health sciencesHealth Professions (all)0302 clinical medicineFuzzy LogicSettore ING-IND/17 - Impianti Industriali MeccaniciService quality benchmarkingHumans030212 general & internal medicineELECTRESettore ING-IND/16 - Tecnologie E Sistemi Di LavorazioneELECTRE IIIQuality of Health CareService (business)Service quality030503 health policy & servicesHealthcare qualityBenchmarkingELECTRE III; Fuzzy set theory; Healthcare quality; IPA; Service quality benchmarking; Service quality management; Medicine (miscellaneous); Health Professions (all)Settore ING-IND/35 - Ingegneria Economico-GestionaleBenchmarkingItalyIPAModels OrganizationalGeneral Health ProfessionsFuzzy set theory0305 other medical scienceHealth care management science
researchProduct

Linguistic Approach to Support Human Reliability Analysis and Validation Work in Advanced Radiotherapy Technologies

2019

An integrated methodology, that combines Hierarchical Task Analysis (HTA), Cognitive Task Analysis (CTA) and a modified Human Error Assessment and Reduction Technique (HEART), is proposed to identify safety-relevant human actions in innovative and advanced facilities. It is suggested to use in HEART the concept of linguistic expressions for proportion assessment factors. To prove its applicability, a case study is presented. The validation work has related to safety analyses of accidental events that can involve radiological over-exposure of patients during proton therapy treatments carried out by CATANA (Centro di AdroTerapia Applicazioni Nucleari Avanzate) centre, Italy. CATANA is the fir…

Operator human errorAdrotherapyWork (electrical)Computer scienceTask analysisHEARTCentro di AdroTerapia Applicazioni Nucleari AvanzateHuman error assessment and reduction techniqueProton therapySettore ING-IND/19 - Impianti NucleariLinguisticsHierarchical Task AnalysiHuman reliability
researchProduct