0000000000513873

AUTHOR

Mariarosa Giardina

showing 87 related works from this author

Misure spettrometriche gamma di concentrazioni radionuclidiche in campioni ambientali e alimentari in situazioni di emergenza

2013

Settore ING-IND/20 - Misure E Strumentazione Nuclearispettrometria gamma campioni ambientali emergenzaSettore ING-IND/19 - Impianti Nucleari
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Uso integrato di metodologie FMEA, HAZOP e FAULT TREE nella windowless target unit di un Accelerator Driven System

2004

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FUZZY RISK ANALYSIS OF A MODERN γ-RAY INDUSTRIAL IRRADIATOR

2011

Fuzzy fault tree analyses were used to investigate accident scenarios that involve radiological exposure to operators working in industrial γ-ray irradiation facilities. The HEART method, a first generation human reliability analysis method, was used to evaluate the probability of adverse human error in these analyses. This technique was modified on the basis of fuzzy set theory to more directly take into account the uncertainties in the error-promoting factors on which the methodology is based. Moreover, with regard to some identified accident scenarios, fuzzy radiological exposure risk, expressed in terms of potential annual death, was evaluated. The calculated fuzzy risks for the examine…

EpidemiologyComputer scienceHealth Toxicology and MutagenesisFuzzy setHuman errorRadiation DosageRisk AssessmentFuzzy fault treeFuzzy logicFirst generationReliability engineeringFuzzy LogicGamma RaysOccupational ExposureRadiological weaponHumansIndustryRadiology Nuclear Medicine and imagingFuzzy risk analysisProbabilityHuman reliabilityHealth Physics
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Safety studies of a hydrogen refuelling station: Determination of the occurrence frequency of the accidental scenarios

2009

At present, the hydrogen vehicles technology appears to have future Prospective for reduction in greenhouse gas emissions. Nevertheless, the development of such a technology requires appropriate infrastructures for production, Storage and refuelling stages in a refuelling station. This one presents safety challenges due to the hydrogen chemicophysical characteristics. So, to avoid hazards, it is necessary to implement safety practices that, if early adopted in the development of a fuelling station project, can allow very low impact, safety being incorporated in the project itself. However, a drawback is the not sufficient experience and the scarcity of the relevant data collection. To deepe…

Fault tree analysesRenewable Energy Sustainability and the EnvironmentHazard and operability studyEnergy Engineering and Power TechnologyCondensed Matter PhysicsHazardHydrogen vehicleHydrogen refuelling stationRisk analysiFuel TechnologyWork (electrical)Risk analysis (engineering)Risk analysis (business)Greenhouse gasEnvironmental scienceHAZOPRisk assessmentFMEASettore ING-IND/19 - Impianti NucleariDrawbackInternational Journal of Hydrogen Energy
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A semi-empirical approach for predicting two-phase flow discharge through branches of various orientations connected to a horizontal main pipe

2010

Abstract The subdivision of two-phase flow in branching conduits consisting of a large horizontal main pipe with upward, downward, or lateral branches of reduced diameter is of great interest in various technological fields. For example, these conduits are important in light-water nuclear reactors (LWRs) in the case of a small break loss-of-coolant accident (SBLOCA) in a leg of the reactor's primary coolant loops, as well as for breaks or valve malfunctions in a large pipeline. In these kinds of circumstances, the relevant phenomenology often involves phase stratification coupled with possible liquid entrainment or gas pool-through phenomena. Therefore, these phenomena were studied in depth…

Nuclear and High Energy PhysicsEngineeringStratification (water)STRATIFIED FLOWREGIONElectrical conduitTUBESSMALL BREAKForensic engineeringMass flow rateGeneral Materials ScienceDUAL DISCHARGESafety Risk Reliability and QualityWaste Management and DisposalINCLINED PLANESettore ING-IND/19 - Impianti NucleariSubdivisionPressure dropONSETSbusiness.industryMechanical EngineeringMechanicsLIQUID ENTRAINMENTCoolantNuclear Energy and EngineeringGASPATTERNSTwo-phase flowbusinessNuclear Engineering and Design
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A Review of Healthcare Failure Mode and Effects Analysis (HFMEA) in Radiotherapy

2016

This paper presents a review of risk analyses in radiotherapy (RT) processes carried out by using Healthcare Failure Mode Effect Analysis (HFMEA) methodology, a qualitative method that proactively identifies risks to patients and corrects medical errors before they occur. This literature review was performed to provide an overview of how to approach the development of HFMEA applications in modern RT procedures, comparing recently published research conducted to support proactive programs to identify risks. On the basis of the reviewed literature, the paper suggests HFMEA shortcomings that need to be addressed.

medicine.medical_specialtyRadiology Nuclear Medicine and ImagingEpidemiologyHealth Toxicology and MutagenesisMEDLINESensitivity and Specificity030218 nuclear medicine & medical imagingrisk estimate03 medical and health sciences0302 clinical medicineNeoplasmsHealth caremedicineHumansMedical physicsHealthcare Failure Mode and Effect Analysisrisk analysiRadiation InjuriesradiotherapySettore ING-IND/19 - Impianti NucleariRadiation medicalMedical Errorsbusiness.industryReproducibility of ResultsSurvival Rate030220 oncology & carcinogenesisbusinessFailure mode and effects analysis
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Analysis of operator human errors in hydrogen refuelling stations: Comparison between human rate assessment techniques

2013

Abstract The use of hydrogen as an energy carrier for road transport appears to be an optimal solution for the reduction of greenhouse gas emissions. Nevertheless, the development of this technology depends on the growth and diffusion of production, storage and refuelling infrastructures together with accurate risk analyses to appropriately design the safety and management systems used in these plants. Moreover, to improve safety standards, it is also important to focus attention on the estimation of hazards related to human factors, as this is one of the major causes leading to accidental events, especially in complex industrial technology. The paper reports a case study relevant to operat…

Energy carrierRisk analysisRenewable Energy Sustainability and the EnvironmentComputer scienceFuzzy setFuzzy HEARTEnergy Engineering and Power TechnologySafety standardsCondensed Matter PhysicsHydrogen refuelling stationReliability engineeringRisk analysiFuel TechnologyIndustrial technologyGreenhouse gasManagement systemStorage unitHuman errorHuman error assessment and reduction techniqueCREAMSettore ING-IND/19 - Impianti Nucleari
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Analysis of Protected Accidental Transients in the EFIT Reactor With the RELAP5 Thermal-Hydraulic Code

2008

The European Facility for Industrial Transmutation (EFIT) is aimed at demonstrating the feasibility of transmutation process through the Accelerator Driven System (ADS) route on an industrial scale. The conceptual design of this reactor of about 400 MW thermal power is under development in the frame of the European EUROTRANS Integrated Project of the EURATOM Sixth Framework Program (FP6). EFIT is a pool-type reactor cooled by forced circulation of lead in the primary system where the heat is removed by steam generators installed inside the reactor vessel. The reactor power is sustained by a spallation neutron source supplied by a proton beam impinging on a lead target at the core centre. A …

EFIT reactor RELAP5 thermal-hydraulic code protected accidental transientsEngineeringNuclear transmutationWaste managementbusiness.industryNuclear engineeringThermal power stationHeat sinkThermal hydraulicsNatural circulationDecay heatbusinessReactor pressure vesselSettore ING-IND/19 - Impianti NucleariThermal energyVolume 3: Thermal Hydraulics; Instrumentation and Controls
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THERP and HEART integrated methodology for human error assessment

2014

Medical errors are one of the leading causes of death and injury in radiation therapy administration as reported in the literature. This point out an overall deficiency in management allowing patient treatment in the absence of suitable quality assurance processes. Clinical records of major accidental exposure events in radiotherapy show that there is a combination of factors contributing to the accident such as deficient staff training, lack of independent checks, lack of quality control procedures, and absence of overall supervision. Another finding is that training generally addresses only normal situations and does not prepare radiotherapy staff for unusual situations, resulting in a la…

radiation therapy patient safety human errors fuzzy THERP.Settore ING-IND/20 - Misure E Strumentazione NucleariSettore ING-IND/19 - Impianti Nucleari
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Modifiche al codice RELAP5 per l’analisi termofluidodinamica monofase delle perdite di carico in scambiatori di calore a tubi elicoidali

2009

codice RELAP5 perdite di caricotubi elicoidali
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Rewetting of a hot vertical surface by liquid sprays

2005

Hot surfaces rewetting interests several technological fields. A very important application is in nuclear reactors technology, where it governs the cooling of overheated fuel elements during hypothesized loss of coolant accidents (LOCAs). This phenomenon is also important in many normal processes and accidental situations taking place in conventional processes. For example when the integrity of metallic containers, filled by toxic or dangerous substances, is endangered by a hypothetical fire. The rewetting consists in the re-establishment of coolant in contact with metallic surfaces become dried due to high temperature. To this end cold liquid is injected on these surfaces via sprays or other …

Fluid Flow and Transfer ProcessesMechanical EngineeringGeneral Chemical EngineeringNuclear engineeringAerospace EngineeringCoolantSubcoolingNuclear Energy and EngineeringContainmentAccident managementloss of coolant accidents liquid sprays hot surface rewettingHeat transferEnvironmental scienceModel setSettore ING-IND/19 - Impianti NucleariCooling fluid
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ICONE19-43144 RELAP5 SIMULATION OF TWO-PHASE FLOW EXPERIMENTS IN VERTICAL HELICAL TUBES

2011

Pressure dropMaterials sciencemedicine.anatomical_structuremedicineTwo-phase flowMechanicsIris (anatomy)The Proceedings of the International Conference on Nuclear Engineering (ICONE)
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Atmospheric dry deposition processes of particles on urban and suburban surfaces: Modelling and validation works

2019

Abstract Dry deposition process is one of the important pathways for the removal of particles from atmosphere. It is the result of a combination of different environmental and physical factors as atmospheric conditions, particle properties, characteristics of the canopy. For this latter factor, urban canopy represents unevenly combinations of different types of surface elements that increases the complexity of deposition process phenomena. Therefore, particle dry deposition on urban surfaces is not easy to configure and, although empirical or semi-empirical models in literature have been developed to address this aspect, there is not standardized and commonly accepted criteria, especially f…

Urban surfaceCanopyAtmospheric ScienceBrownian diffusion resistance; Coarse particles; Dry deposition process; Nuclear power plant accidents; Submicron particles; Urban canopy010504 meteorology & atmospheric sciencesNuclear power plant accidentCoarse particlesNuclear power plant accidents010501 environmental sciencesAtmospheric sciences01 natural sciencesUrban canopyAtmosphereSurface roughnessBrownian diffusion resistanceSubmicron particlesDry deposition proceSettore ING-IND/19 - Impianti Nucleari0105 earth and related environmental sciencesGeneral Environmental ScienceDry deposition processParticle propertiesCoarse particleSubmicron particleUrban canopyDry deposition processUrban canopyBrownian diffusion resistanceNuclear power plant accidentsCoarse particlesSubmicron particlesParticleEnvironmental scienceDeposition process
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Prediction of the heat exchange in MEGAPIE facility by using RELAP5 code

2008

RELAP5 Lead-Bismuth Eutectic Accelerator Driven Systemsspallation target
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RPN safety analysis to reduce the risk of malpractices in high dose rate brachytherapy

2013

A new fuzzy rule-based assessment model is proposed to evaluate the risk priority number in the Failure Mode, Effects, and Criticality Analysis (FMECA) method to rank component failures and human errors from the medical staff, leading to potential radiological over-exposure of patients during high-dose-rate brachytherapy treatment. The obtained results are relevant for a range of causes that have a reasonable probability of producing significant adverse outcomes. Thus, recommendations are provided for procedures and safety devices to reduce the occurrence of radiological over-exposure accidents. This method can solve the problems in conventional FMECA applications and improve the safety and…

RPN FMECA BRACHYTHERAPY RISKSettore ING-IND/19 - Impianti Nucleari
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A new approach for modeling dry deposition velocity of particles

2018

Abstract The dry deposition process is recognized as an important pathway among the various removal processes of pollutants in the atmosphere. In this field, there are several models reported in the literature useful to predict the dry deposition velocity of particles of different diameters but many of them are not capable of representing dry deposition phenomena for several categories of pollutants and deposition surfaces. Moreover, their applications is valid for specific conditions and if the data in that application meet all of the assumptions required of the data used to define the model. In this paper a new dry deposition velocity model based on an electrical analogy schema is propose…

PollutionAtmospheric ScienceInertial frame of reference010504 meteorology & atmospheric sciencesmedia_common.quotation_subjectDry deposition velocityParticle flux010501 environmental sciences01 natural sciencesParticle fluxMutual influenceSettore ING-IND/19 - Impianti Nucleari0105 earth and related environmental sciencesGeneral Environmental Sciencemedia_commonPollutant2300TurbulenceParametrizationMechanicsAtmospheric dispersion modelingDry deposition velocity; Parametrization; Particle flux; Radioactive pollutants; Removal processes; 2300; Atmospheric ScienceRadioactive pollutantDeposition (aerosol physics)Environmental scienceRemoval processe
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Analisi di sicurezza e valutazione dell’errore umano nelle procedure di manutenzione del sistema di stoccaggio in un autobus a metano

2010

AUTOBUS A METANO ANALISI DI SICUREZZA ERRORE UMANO
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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
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Analysis of radionuclide concentration in air released through the stack of a radiopharmaceutical production facility based on a medical cyclotron

2015

Abstract Positron emitting radionuclides are increasingly used in medical diagnostics and the number of radiopharmaceutical production facilities have been estimated to be growing worldwide. During the process of production and/or patient administration of radiopharmaceuticals, an amount of these radionuclides might become airborne and escape into the environment. Therefore, the analysis of radionuclide concentration in the air released to the stack is a very important issue to evaluate the dose to the population living around the plant. To this end, sampling and measurement of radionuclide concentration in air released through the stack of a Nuclear Medicine Center (NMC), provided with a c…

education.field_of_studyRadionuclideMedical diagnosticRadiationSettore ING-IND/20 - Misure E Strumentazione NucleariChemistrySystem of measurementNuclear engineeringPopulationDetectorCyclotronSampling (statistics)law.inventionStack (abstract data type)lawMedical cyclotron PET Radioactive air effluent RadiopharmaceuticalseducationSettore ING-IND/19 - Impianti NucleariNuclear chemistryRadiation Physics and Chemistry
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Early-design improvement of human reliability in an experimental facility: A combined approach and application on SPES

2019

Abstract SPES (Selective Production of Exotic Species) is a second-generation Isotope Separation On-Line (ISOL) facility for advanced nuclear physics applications, currently under construction at INFN (National Institute of Nuclear Physics) of Legnaro, Italy. Despite the potentially important safety implications of human errors for ISOL facilities, only a limited number of studies addressing this issue have been performed worldwide. This paper tries to address this need by means of an integrated approach of Hierarchical Task Analysis (HTA) and three human error quantification methods: HEART (in an enhanced version), SPAR-H, and CREAM. The application of multiple Human Reliability Analysis (…

Interface (Java)Computer scienceHuman error0211 other engineering and technologies02 engineering and technologyTask (project management)law.inventionlawHuman reliability assessment021105 building & constructionNuclear power plantCredibilityHuman error0501 psychology and cognitive sciencesHierarchical task analysiSafety Risk Reliability and QualitySettore ING-IND/19 - Impianti Nucleari050107 human factorsHuman reliability05 social sciencesPublic Health Environmental and Occupational HealthSPAR-HControl roomTask analysisSystems engineeringHEARTCREAMSafety ResearchSafety Science
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FMECA Application in Tomotherapy: Comparison between Classic and Fuzzy Methodologies

2022

Accident analysis in radiotherapy highlighted the need to increase quality assurance (QA) programs by the identification of failures/errors with very low probability (rare event) but very severe consequences. In this field, a Failure Mode, Effects and Criticality Analysis (FMECA) technique, used in various industrial processes to rank critical events, has been met with much interest. The literature describes different FMECA methods; however, it is necessary to understand if these tools are incisive and effective in the healthcare sector. In this work, comparisons of FMECA methodologies in the risk assessment of patients undergoing treatments performed with helical tomotherapy are reported. …

risk assessment; FMEA; FMECA; radiotherapy; health physics; fuzzy risk priority numberRenewable Energy Sustainability and the Environmentfuzzy risk priority numberEcology Evolution Behavior and SystematicsFMEAradiotherapySettore ING-IND/19 - Impianti NucleariGeneral Environmental ScienceRisk assessmentFMECAhealth physics
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Fuzzy environmental analogy index to develop environmental similarity maps for designing air quality monitoring networks on a large-scale

2019

All activities aimed at studying the primary causes and effects of air pollution cannot disregard the fact that it is necessary to have an optimal air quality monitoring network for assessing population exposure to air pollution and predicting the magnitude of the health risks. In the framework of a cooperation between the ARPA Sicilia Organization and the Department of Engineering, University of Palermo, research was performed to develop an innovative methodology useful for defining environmental similarity maps aimed at supporting the design of air quality monitoring networks at the regional scale. This approach is based on a new index called the fuzzy environmental analogy index (FEAI) b…

Environmental EngineeringIndex (economics)010504 meteorology & atmospheric sciencesComputer scienceAnthropogenic or natural impact0208 environmental biotechnologyAir pollutionAnalogyComputational intelligence02 engineering and technologymedicine.disease_cause01 natural sciencesFuzzy logicEnvironmental similarity mapSimilarity (psychology)medicineEnvironmental ChemistrySafety Risk Reliability and QualityAir quality indexSettore ING-IND/19 - Impianti Nucleari0105 earth and related environmental sciencesGeneral Environmental ScienceWater Science and TechnologyAir quality monitoring networkbusiness.industryScale (chemistry)Environmental resource managementEnvironmental pressure020801 environmental engineeringFuzzy environmental analogy indexbusinessStochastic Environmental Research and Risk Assessment
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Fuzzy fault tree analysis in modern γ-ray industrial irradiator: Use of fuzzy version of HEART and CREAM techniques for human error evaluation

2008

As well known, the lack of accurate quantitative human reliability data is a serious limitation and source of uncertainty in risk assessment. Therefore, in the last years, many Authors suggested that the use of the fuzzy sets theory can fill up this gap, performing as useful tool when dealing with qualitative or vague information. In such a framework, 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 γ-ray irradiation industrial plant. For these analyses the HEART methodology, a first generation HRA (Human Reliability Analysis) method, has been employed to evaluate the proba…

Fuzzy fault tree analysiIrradiation industrial plantHEARTCREAMSettore ING-IND/19 - Impianti Nucleari
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Thermal-hydraulic analysis on the cooling system of the target in the SPES plant

2012

Settore ING-IND/19 - Impianti NucleariThermal-hydraulic analysis cooling system SPES
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RELAP5 Modification for CHEOPE Simulations

2005

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A new tool to process forecast meteorological data for atmospheric pollution dispersion simulations of accident scenarios: A Sicily-based case study

2021

Emergency response plans to mitigate the severity of the accidental release of hazardous compounds in the air have become a primary concern in view of the many adverse events occurred over the years in high-risk plants. To do this, an accurate estimate of forecast meteorological data to be used in dispersion models can be very useful to respond in advance to emergency situations. In this field, FORCALM is a new tool developed to elaborate European Centre for Medium-Range Weather Forecasts data on a 3D computational domain with a high-resolution grid. FORCALM data can be used to perform predictive simulations of impacts on local and regional levels by using CALPUFF modelling system. A case s…

TechnologySettore ING-IND/11 - Fisica Tecnica AmbientaleAir pollution; Forecast meteorological data; Dispersion model; Risk analysis; High-risk plantMeteorologyRenewable Energy Sustainability and the EnvironmentProcess (engineering)risk analysisTair pollutionAir pollutionEnergy Engineering and Power TechnologyAtmospheric pollutionEconomic growth development planningEnvironmental Science (miscellaneous)medicine.disease_causehigh-risk plants.Based case studydispersion modelmedicineHD72-88Environmental scienceStatistical dispersionAir pollution Forecast meteorological data Dispersion model Risk analysis High-risk plants.forecast meteorological dataWater Science and TechnologyJournal of Sustainable Development of Energy, Water and Environment Systems
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Risk analysis using fuzzy set theory of accidental exposure of medical staff during brachytherapy procedures

2010

Using fuzzy set theory, this paper presents results from risk analyses that explore potential exposure of medical operators working in a high dose rate brachytherapy irradiation plant. In these analyses, the HEART methodology, a first generation method for human reliability analysis, has been employed to evaluate the probability of human error. This technique has been modified on the basis of fuzzy set concepts to take into account, more directly, the uncertainties of the so-called error-promoting factors on which the method is based. Moreover, with regard to some identified accident scenarios, fuzzy potential dose was also evaluated to estimate the relevant risk. The results also provide s…

Risk analysisaccidental exposureSafety ManagementSettore ING-IND/20 - Misure E Strumentazione Nuclearimedicine.medical_treatmentFuzzy setHuman errorBrachytherapybrachytherapyRadiation DosageFuzzy logicRisk AssessmentRisk analysiRadiation ProtectionFuzzy LogicRadiation MonitoringOccupational ExposureMedicineHumansRadiation InjuriesRadiometryWaste Management and DisposalSettore ING-IND/19 - Impianti NucleariHuman reliabilityMedical Errorsbusiness.industryPublic Health Environmental and Occupational HealthEquipment Failure AnalysisGeneral MedicineEquipment Failure AnalysisRisk analysis (engineering)Radiological weaponbusinessRadioactive Hazard Release
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Modifiche del Codice RELAP5 per lo Studio delle Perdite di Carico in Generatori di Vapore a Tubi Elicoidali Interessati da Flussi Bifase

2010

RELAP5Settore ING-IND/19 - Impianti Nucleari
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MELCOR per lo Studio Integrale di Sequenze Incidentali su Reattori PWR da 900 MWe e valutazioni preliminari d'impatto a breve e medio raggio

2014

Il presente documento è stato preparato nel corso della seconda annualità dell'AdP ENEA-MSE nell'ambito dell'obiettivo B-Task B_1 (Sviluppo di una Metodologia per Valutazioni di Sicurezza in Condizioni Incidentali o di Pre-Emergenza) della Linea Progettuale 1 (Sviluppo competenze scientifiche nel campo della sicurezza nucleare). Esso riporta i principali risultati della simulazione MELCOR di un transitorio del tipo “short term Station Blackout (SBO)” con possibile rottura dei tubi a U del GV (Steam Generator Tube Rupture - SGTR) indotta da stress termici e un lavoro preliminare di raccolta di informazioni sulle potenzialità presentate da alcune piattaforma di simulazione ad oggi utilizzate …

simulazione MELCOR calpuff calmet frames MM5Settore ING-IND/19 - Impianti Nucleari
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TRACE input model for SPES3 facility

2010

TRACESettore ING-IND/19 - Impianti Nucleari
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Esposizione potenziale in impianti di irraggiamento: un’analisi mediante probabilità di tipo sfumato

2004

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Studies of thermalfluid-dynamic phenomenologies in high energy industrial systems during accidental transients

2004

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The TREEZZY2 Computer Code for Fault Tree and Event Tree Analyses with Fuzzy Probabilities

2004

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Studio della sicurezza di una stazione di rifornimento di idrogeno per autotrazione mediante l’uso integrato di tecniche di analisi di rischio

2008

HAZOP FMEA FAULT TREE
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Pre-conceptual design of EU-DEMO Divertor primary heat transfer systems

2021

Abstract In the frame of the activities promoted and encouraged by the EUROfusion Power Plant Physics and Technology (PPPT) department aimed at developing the EU-DEMO fusion reactor, strong emphasis has been recently addressed to the whole Balance of Plant (BoP) which represents the set of systems devoted to convert the plasma generated thermal power into electricity and to deliver it to the grid. Among these systems, the Divertor Primary Heat Transfer Systems (PHTSs) are intended to feed coolant to the two main components of the Divertor assembly, namely the Plasma Facing Components (PFCs) and the Cassette Body (CB). Since the DEMO Divertor must withstand high heat flux loads together with…

Balance of plantPower stationMechanical EngineeringNuclear engineeringDivertorThermal power stationBlanketFusion power01 natural sciences010305 fluids & plasmasCoolantDivertorNuclear Energy and EngineeringConceptual design0103 physical sciencesHeat exchangerPHTSGeneral Materials Science010306 general physicsDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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Thermalhydraulic analyses of overpower transients in the EFIT reactor

2008

EFIT REACTORSAFETY ANALYSES RELAP5 CODE
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Qualifica di codici di calcolo dedicati alle analisi di sistema avanzati quando applicati nella simulazione di impianti a metallo liquido

2013

generation iv relap termofluidodinamica avanzataSettore ING-IND/19 - Impianti Nucleari
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Safety analysis in the system cyclotron-target unit of the LBE-Cooled XADS plant through an integrated use of FMEA, HAZOP and FAULT TREE methodologies

2004

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Safety study of an LNG regasification plant using an FMECA and HAZOP integrated methodology

2015

Abstract A safety analysis was performed to determine possible accidental events in the storage system used in the liquefied natural gas regasification plant using the integrated application of failure modes, effects and criticality analysis (FMECA) and hazard and operability analysis (HAZOP) methodologies. The goal of the FMECA technique is the estimation of component failure modes and their major effects, whereas HAZOP is a structured and systematic technique that provides an identification of the hazards and the operability problems using logical sequences of cause-deviation-consequence of process parameters. The proposed FMECA and HAZOP integrated analysis (FHIA) has been designed as a …

Hazard (logic)EngineeringOperabilityHazard and operability studyGeneral Chemical EngineeringEnergy Engineering and Power TechnologyManagement Science and Operations ResearchIndustrial and Manufacturing EngineeringRisk analysiRisk analysis (business)Human errorSettore ING-IND/10 - Fisica Tecnica IndustrialeSafety Risk Reliability and QualitySettore ING-IND/19 - Impianti NucleariRegasificationbusiness.industryReliability engineeringFailure mode effects and criticality analysisControl and Systems EngineeringSystems engineeringLNGHAZOPRisk priority numberbusinessFailure mode and effects analysisRegasification terminalFood ScienceLiquefied natural gasFMECA
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THERP and HEART integrated methodology for human error assessment

2015

Abstract THERP and HEART integrated methodology is proposed to investigate accident scenarios that involve operator errors during high-dose-rate (HDR) treatments. The new approach has been modified on the basis of fuzzy set concept with the aim of prioritizing an exhaustive list of erroneous tasks that can lead to patient radiological overexposures. The results allow for the identification of human errors that are necessary to achieve a better understanding of health hazards in the radiotherapy treatment process, so that it can be properly monitored and appropriately managed.

RadiationComputer scienceProcess (engineering)Medical cyclotronHuman errorFuzzy setTechnique for Human Error Rate PredictionFuzzy logicReliability engineeringIdentification (information)PETRadiotherapy treatmentRadiopharmaceuticalsRadioactive air effluentSettore ING-IND/19 - Impianti Nucleari
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Applicazione della tecnica HFMEA in radioterapia

2014

hfmea radioterapiaSettore ING-IND/20 - Misure E Strumentazione NucleariSettore ING-IND/19 - Impianti Nucleari
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Studi di sicurezza con metodologie ad albero di guasti riguardanti l’esposizione potenziale di un operatore in un reparto di brachiterapia

2006

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Analysis of radionuclide concentration in air released through the stack of a radiopharmaceutical production facility

2014

The quantities of positron emitting radionuclides used in medical diagnostics and the number of radiopharmaceutical production facilities have been estimated to be growing worldwide. In this field, an amount of these radionuclides might become airborne and escape into the environment during the process of production and/or during administration by hospital personnel. Therefore, the analysis of dose to the operating staff as well as to the public, due to releases through the stack, is a very important issue. To this end, sampling and measurement of radionuclide concentration in air released through the stack of a Nuclear Medicine Center (NMC), provided with a cyclotron for radiopharmaceutica…

Medical cyclotron radioactive air effluent PET Potential dose.Settore ING-IND/20 - Misure E Strumentazione Nucleari
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Analisi Mediante Il Codice TRACE Delle Principali Fenomenologie Caratterizzanti Il Transitorio Conseguente Ad Una Rottura A Ghigliottina Nella Linea …

2011

SPES-3Settore ING-IND/19 - Impianti NucleariDVI break
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FMECA Analyses of radiological over-exposure accident to patients in brachytherapy

2012

This paper presents safety analyses of accidental events which can involve patient during High Dose Rate brachytherapy treatment in over-exposures. The study has been performed by using the well-known techniques FMECA modified by Fuzzy logic theory. Moreover, fuzzy HEART methodology was employed in order to evaluate human error probabilities for each treatment stage. The obtained results, aimed to obtain a list of the deviations with a reasonable probability to produce significant adverse outcomes, provided some recommendations for procedures and safety equipments to reduce the occurrence of radiological over-exposure accidents.

Settore ING-IND/20 - Misure E Strumentazione NucleariSettore ING-IND/19 - Impianti NucleariHigh Dose Rate radiation therapy radiological risk FMECA fuzzy RPN
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Fuzzy FMECA analysis of radioactive gas recovery system in the SPES experimental facility

2021

Abstract Selective Production of Exotic Species is an innovative plant for advanced nuclear physic studies. A radioactive beam, generated by using an UCx target-ion source system, is ionized, selected and accelerated for experimental objects. Very high vacuum conditions and appropriate safety systems to storage exhaust gases are required to avoid radiological risk for operators and people. In this paper, Failure Mode, Effects, and Criticality Analysis of a preliminary design of high activity gas recovery system is performed by using a modified Fuzzy Risk Priority Number to rank the most critical components in terms of failures and human errors. Comparisons between fuzzy approach and classic…

Computer scienceSPES FMECA Fuzzy Risk Priority Number evidence theory exhaust gas storage system020209 energySystem safety02 engineering and technologyFuzzy logicFuzzy risk priority numberPriority Number030218 nuclear medicine & medical imaging03 medical and health sciences0302 clinical medicine0202 electrical engineering electronic engineering information engineeringSettore ING-IND/19 - Impianti NucleariRank (computer programming)TK9001-9401SPESExhaust gas storage systemReliability engineeringEvidence theoryFailure mode effects and criticality analysisNuclear Energy and EngineeringNuclear engineering. Atomic powerRisk assessmentFailure mode and effects analysisRadioactive gasFMECANuclear Engineering and Technology
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RELAP5 simulation of two-phase flow experiments in vertical helical tubes

2010

In the framework of the studies concerning the thermalfluid dynamic phenomena in helicoidal pipes of the innovative nuclear reactor IRIS steam generators, the Department of Nuclear Engineering of the University of Palermo in collaboration with the Politecnico di Torino Department of Energetics has been engaged in a work aimed to adapt, by implementing new suitable models, RELAP5/mod3.2.2β code to simulate the thermalfluid-dynamics and geometries such as the ones involved in helicoidal pipes. In fact this code is based on one-dimensional thermal-hydraulic relationships and presents limitations to model complicated geometry such as helicoidal pipes. Therefore the code was improved with additi…

relaphelical tubes two-phase flowSettore ING-IND/19 - Impianti Nucleari
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Esposizione potenziale dell’operatore in un impianto dotato di acceleratore: studio mediante l’uso di tecniche ad albero di guasto di tipo sfumato

2006

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Analyses of single- and two-phase flow pressure drops in helical pipes using a modified RELAP5 code

2012

Abstract Thermal fluid dynamics analyses on single- and two-phase flows in helical pipes of steam generators to be used in Generation III and IV nuclear reactors have been performed. The study concerned with experimental activities as well code simulations carried out in the framework of a collaboration between the Department of Energetics of the Polytechnic of Torino and the Department of Energy of the University of Palermo. The goal was the validation of models implemented in Relap5/Mod3.2β thermal–hydraulic advanced code to simulate the hydrodynamic behaviour of helical pipe components in spite of the one-dimensional nature of the code. It is shown that much of the experimental data obta…

Nuclear and High Energy PhysicsEngineeringHydraulicsNuclear engineeringMechanical engineeringReattori nucleari innovativiGeneratori di vapore elicoidalilaw.inventionThermal hydraulicsTUBESlawThermalFluid dynamicsCode (cryptography)General Materials ScienceSafety Risk Reliability and QualityWaste Management and DisposalSettore ING-IND/19 - Impianti NucleariTWO PHASEPressure dropbusiness.industryMechanical EngineeringRELAP5/MOD3.2Fluid mechanicsGeneratori di vapore elicoidali; Reattori nucleari innovativiNuclear Energy and EngineeringHELICOIDAL PIPESTwo-phase flowbusiness
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Decay Heat Removal and Transient Analysis in Accidental Conditions in the EFIT Reactor

2008

The development of a conceptual design of an industrial-scale transmutation facility (EFIT) of several 100 MW thermal power based on accelerator-driven system (ADS) is addressed in the frame of the European EUROTRANS Integral Project. In normal operation, the core power of EFIT reactor is removed through steam generators by four secondary loops fed by water. A safety-related decay heat removal (DHR) system provided with four independent inherently safe loops is installed in the primary vessel to remove the decay heat by natural convection circulation under accidental conditions which are caused by a loss-of-heat sink (LOHS). In order to confirm the adequacy of the adopted solution for decay…

EngineeringNatural convectionNuclear transmutationArticle Subjectbusiness.industryNuclear engineeringMechanical engineeringThermal power stationTransient analysisNatural circulationNuclear Energy and EngineeringConceptual designlcsh:Electrical engineering. Electronics. Nuclear engineeringDecay heatADS EFIT Reactor Transient Analysis SIMMER-III codebusinessReactor pressure vessellcsh:TK1-9971Settore ING-IND/19 - Impianti Nucleari
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Modifiche del codice RELAP5/MOD3.2.b per lo studio delle perdite di carico e dello scambio termico in condotti elicoidali interessati da deflussi bif…

2011

L’attività di ricerca svolta nell’ambito della linea progettuale LP2-B.2 del programma PAR 2008-09 (CERSE III) ha visto una prima fase in cui è stato ulteriormente sviluppato il lavoro svolto nel corso dei precedenti programmi CERSE [1, 2], riguardante la validazione del codice termoidraulico avanzato Relap5/Mod3.2.b, modificato per il calcolo delle cadute di pressione in tubi elicoidali interessati da deflussi monofase e bifase, ed una seconda fase che ha comportato l’implementazione di nuove procedure valide per lo studio dello scambio termico bifase in condotti elicoidali, in aggiunta a quelle relative al solo scambio termico monofase, in precedenza implementate. Per quanto riguarda ques…

Relap5/mod3.2b generation iv LFR condotti elicoidali deflussi bifaseSettore ING-IND/19 - Impianti Nucleari
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Analisi di sicurezza mediante l’uso di tecniche ad alberi di guasto FUZZY dell’impianto nucleare dimostrativo XADS

2006

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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
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Fuzzy risk analysis of a modern gamma-ray industrial irradiator

2011

Fuzzy fault tree analyses were used to investigate accident scenarios that involve radiological exposure to operators working in industrial gamma-ray irradiation facilities. The HEART method, a first generation human reliability analysis method, was used to evaluate the probability of adverse human error in these analyses. This technique was modified on the basis of fuzzy set theory to more directly take into account the uncertainties in the error-promoting factors on which the methodology is based. Moreover, with regard to some identified accident scenarios, fuzzy radiological exposure risk, expressed in terms of potential annual death, was evaluated. The calculated fuzzy risks for the exa…

accidents nuclearaccident analysinuclear power industryemergencies radiologicalSettore ING-IND/19 - Impianti Nucleari
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Education and Research in Nuclear Engineering and Radiological Protection at Nuclear Engineering Department of Palermo University

2010

Education Research Nuclear Engineering Radiological Protection Palermo UniversitySettore ING-IND/19 - Impianti Nucleari
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Thermal hydraulic analyses in the windowless target of an Accelerator Driven System

2004

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Dry deposition of particle on urban areas

2019

Abstract Dry deposition process is recognized as an important pathway among the removal processes of radioactive pollutants in atmosphere. There is not a unique and accepted theoretical description of involved dry deposition phenomena due to the complexity of the fluid-dynamic processes that influence the deposition flux, but also because there is a lack of experimental data covering all scenarios of interest. In this paper, that is the result of a National Research Program a research activity conducted by DEIM Department of the University of Palermo and ENEA and funded by the Italian Minister of Economic Development, a new schema for parameterization of particle dry deposition velocity on …

HistorygeographyDry deposition velocity air pollution urban areasparticle depositiongeography.geographical_feature_categoryDeposition (aerosol physics)Environmental engineeringEnvironmental scienceUrban areaSettore ING-IND/19 - Impianti NucleariComputer Science ApplicationsEducationParticle depositionJournal of Physics: Conference Series
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SAFETY ANALYSES OF POTENTIAL EXPOSURE IN MEDICAL IRRADIATION PLANTS BY FUZZY FAULT TREE

2008

fuzzy fault tree safety analyses irradiation plant
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Valutazione della dose potenziale per alcuni scenari incidentali in un impianto HDR: uso di tecniche di tipo sfumato

2007

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A Training Experience of Operators with the AGN-201 “Costanza” Research Reactor of Palermo University

2011

The nuclear reactor AGN-201 named “Costanza”, installed at the Nuclear Engineering Section of the Department of Energy of the University of Palermo, is a “zero power” research reactor designed to be mainly used for education purposes as well as for research applications, such as activation analysis and irradiation tests, and last, but not the least, for radionuclide production to be used in nuclear medical applications. Due to its intrinsic safety and low margin of reactivity (less than 350 p.c.m.) so as to the absence of start-up and shut-down time limits, it represents a useful training tool for operators, too. This paper reports some of the activities carried out within the framework of …

Settore ING-IND/20 - Misure E Strumentazione NucleariTraining AGN-201 nuclear research reactorSettore ING-IND/19 - Impianti Nucleari
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Analisi di sicurezza nella procedura di protonterapia oculare applicata presso i Laboratori del Sud dell’INFN di Catania

2017

A partire dal 2002, l’Azienda Ospedaliera Universitaria “Policlinico Vittorio Emanuele” di Catania ha effettuato il trattamento di circa 350 pazienti affetti da neoplasie oculari mediante fasci di protoni prodotti con il ciclotrone disponibile presso i Laboratori nazionali del Sud (LNS). Tale impianto viene utilizzato per attività di ricerca nell’ambito della fisica sperimentale, per cui è stato necessario modificare le caratteristiche del fascio, rendendolo idoneo alle applicazioni cliniche. Il lavoro di ricerca ha riguardato lo svolgimento della analisi del rischio volto ad individuare possibili fallimenti nelle procedure adottate per il trattamento del paziente sottoposto a cicli di prot…

Settore ING-IND/20 - Misure E Strumentazione Nucleariprotonterapia Analisi di sicurezza Hierarchical Task Analysis Cognitive Task Analysis Human Error Assessment and Reduction TechniqueSettore ING-IND/19 - Impianti Nucleari
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Dry deposition models for radionuclides dispersed in air: a new approach for deposition velocity evaluation schema

2017

In the framework of a National Research Program funded by the Italian Minister of Economic Development, the Department of Energy, Information Engineering and Mathematical Models (DEIM) of Palermo University and ENEA Research Centre of Bologna, Italy is performing several research activities to study physical models and mathematical approaches aimed at investigating dry deposition mechanisms of radioactive pollutants. On the basis of such studies, a new approach to evaluate the dry deposition velocity for particles is proposed. Comparisons with literature experimental data show that the proposed dry deposition scheme allows to capture the main phenomena involved in the dry deposition process…

HistoryRadionuclidePhysical model010504 meteorology & atmospheric sciencesMathematical modelbusiness.industryChemistryMechanical engineering01 natural sciences010305 fluids & plasmasComputer Science ApplicationsEducationResearch centreDry deposition pollutant radionuclides deposition velocity0103 physical sciencesProcess engineeringbusinessSettore ING-IND/19 - Impianti Nucleari0105 earth and related environmental sciencesJournal of Physics: Conference Series
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Human Reliability Analysis to support operational planning of an experimental facility

2015

This paper reports the results obtained by using different techniques of Human Reliability Analysis (HRA) to identify potential operator errors at the SPES (Selective Production of Exotic Species) facility, a second generation Isotope Separation On Line (ISOL) plant for advanced nuclear physic applications. The paper presents scoping-level HRA applications, with the main goal to evaluate the applicability of HRA techniques for the specific domain. In particular, two aspects challenge a standard HRA. First, the facility is under construction so that a number of aspects related to its operation (e.g. procedures and operator interfaces) are still under definition. Second, the context of operat…

Safety Risk Reliability and QualitySettore ING-IND/19 - Impianti Nucleari
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Analisi di sicurezza mediante l’uso di tecniche ad albero di guasto di tipo sfumato riguardanti l’errata esposizione ad alto rateo di dose di un pazi…

2006

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Multiple failure accidental transients in the LBE-XADS

2005

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Analisi di sicurezza integrata e ricorsiva per l’impianto nucleare dimostrativo XADS

2005

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New Implementations in RELAP5 for Post-Test Analysis of the MEGAPIE Irradiation Phase

2007

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Predicting two-phase flow discharge through branches of various orientation connected to a horizontal main pipe

2008

two-phase flow discharge branch horizontal main pipe
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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
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Modifying RELAP5 code to deal with helical coiled ducts

2006

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Rewetting by liquid spray of a hot metallic wall

2004

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Risk assessment of component failure modes and human errors using a new FMECA approach: application in the safety analysis of HDR brachytherapy

2014

Failure mode, effects and criticality analysis (FMECA) is a safety technique extensively used in many different industrial fields to identify and prevent potential failures. In the application of traditional FMECA, the risk priority number (RPN) is determined to rank the failure modes; however, the method has been criticised for having several weaknesses. Moreover, it is unable to adequately deal with human errors or negligence. In this paper, a new versatile fuzzy rule-based assessment model is proposed to evaluate the RPN index to rank both component failure and human error. The proposed methodology is applied to potential radiological over-exposure of patients during high-dose-rate brach…

HDR brachytherapySafety ManagementComputer sciencemedicine.medical_treatmentBrachytherapyHuman errorBrachytherapyRisk AssessmentRadiation ProtectionComponent (UML)medicineHumansComputer SimulationRadiation InjuriesWaste Management and Disposalhuman errorSettore ING-IND/19 - Impianti Nuclearirisk priority numberModels StatisticalFuzzy ruleMedical ErrorsIncidenceRank (computer programming)Public Health Environmental and Occupational HealthGeneral MedicineReliability engineeringEquipment Failure AnalysisSurvival RateFailure mode effects and criticality analysisEquipment FailurePatient Safetyfuzzy logicRadioactive Hazard ReleaseRisk assessmentFailure mode and effects analysisFMECA
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Flowblockage failures in the EFIT reactor

2011

Flowblockage EFIT reactorSettore ING-IND/19 - Impianti Nucleari
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Recent improvement of RELAP5 as numerical tool for interpretation of thermal-hydraulic experiments

2006

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Safety analysis in the LBE-Cooled XADS plant through an integrated use of HAZOP, FAULT TREE and thermalhydraulic transient analyses

2004

A detailed description of possible accidental scenarios, with their frequency of occurrence and their consequences, taking into account both internal and external causes that might contribute to them, can be attained by using the most important risk analysis methodologies (HAZard and OPerability studies, HAZOP; Event Tree, ET; Fault Tree, FT; etc.). As it is known, the Fault Tree methodology is aimed at the evaluation of the frequency of an undesired accidental event (Top Event, TE), and is used to describe this one as a combination of primary events identified, for example, by a HAZOP analysis [1]. However, the classic HAZOP analysis, while allowing to perform an exhaustive study of the ex…

Event treeHazard (logic)Fault tree analysisOperabilityComputer scienceHazard and operability studyRisk analysis (business)Event (computing)Transient (oscillation)Reliability engineering
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Dividing two-phase flow in branching conduits with large diameter horizontal main pipes and lateral branches

2004

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RELAP5-3D thermal hydraulic analysis of the target cooling system in the SPES experimental facility

2014

The SPES (Selective Production of Exotic Species) experimental facility, under construction at the Italian National Institute of Nuclear Physics (INFN) Laboratories of Legnaro, Italy, is a second generation Isotope Separation On Line (ISOL) plant for advanced nuclear physic studies. The UCx target-ion source system works at temperature of about 2273 K, producing a high level of radiation (10^5 Sv/h), for this reason a careful risk analysis for the target chamber is among the major safety issues. In this paper, the obtained results of thermofluid-dynamics simulations of accidental transients in the SPES target cooling system are reported. The analysis, performed by using the RELAP5-3D 2.4.2 …

HistoryEngineeringSystem codeRELAP5target cooling systemthermo-fluid-dynamics simulationbusiness.industrySource systemNuclear engineeringMechanical engineeringSPESsafety analysiComputer Science ApplicationsEducationIsotope separationlaw.inventionThermal hydraulicsPhysics and Astronomy (all)RELAP5; safety analysis; SPES; target cooling system; thermo-fluid-dynamics simulations; Physics and Astronomy (all)lawWater coolingbusinessSettore ING-IND/19 - Impianti Nucleari
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Thermalhydraulic analyses of overpower transients without proton beam trip in the XADS facility

2004

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Analisi di sicurezza di una stazione di rifornimento di idrogeno per autotrazione:uso delle tecniche FMEA e HAZOP

2007

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Studio con il codice RELAP5 delle perdite di carico e dello scambio termico in tubi elicoidali interessati da deflussi monofase

2009

codice RELAP5 perdite di carico deflussi monofase
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Verification of the RELAP5 code against the MEGAPIE irradiation experiment

2009

RELAP5 code MEGAPIE irradiation experiment
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RELAP5 simulations for CIRCE experiments

2007

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PROVE ED ESPERIMENTI DI VERIFICA DELLA SICUREZZA DEL REATTORE NUCLEARE DI RICERCA AGN-201 “COSTANZA”

2011

The “Zero Power” Nuclear Reactor AGN-201 “Costanza” available at Nuclear Engineering Department of Palermo University is a valuable tool for educational purpose and research. Besides being a useful tool for training of operators, without the time period limits on start-up and shut-down of the larger reactors, it allows the study of some phenomena regarding nuclear reactor physics, applied neutronics, neutron dosimetry, nuclear measurements as well as testing of nuclear instrumentation and methods. The experience of work and the obtained results highlight the simplicity of AGN-201 reactor control, its intrinsic safety and its overall versatility in various fields of Nuclear Engineering.

reattore AGN-201 COSTANZASettore ING-IND/20 - Misure E Strumentazione NucleariSicurezza nucleareSettore ING-IND/19 - Impianti Nucleari
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TREEZZY2, a Fuzzy Logic Computer Code for Fault Tree and Event Tree Analyses

2004

In conventional approach to reliability analysis using logical trees methodologies, uncertainties in system components or basic events failure probabilities are approached by assuming probability distribution functions. However, data are often insufficient for statistical estimation, and therefore it is required to resort to approximate estimations. Moreover, complicate calculations are needed to propagate uncertainties up to the final results. In our work, in order to take account of the uncertainties in system failure probabilities, the methodology based on fuzzy sets theory is used both in fault tree and event tree analyses. This paper just presents our work in this issue, which resulted…

Probabilistic Safety Assessment
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Risk analysis of the storage unit in a hydrogen refuelling station

2007

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Uso di formulazioni della metodologia cream per la trattazione dell’errore umano nella valutazione ad alberi di guasto della probabilita’ di esposizi…

2008

Analisi di sicurezza impianto di irraggiamento gamma errore umano
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Maintenance Operation on AGN-201 “COSTANZA” Nuclear Research Reactor of Palermo University

2015

During operations with AGN-201 “COSTANZA” nuclear research reactor of Palermo University a failure of a compensated boron-lined ionization chamber provided with a measurement channel was highlighted. A maintenance program aimed to verify the operative conditions of all measurement systems was then started. It was easy to identify as cause of the malfunction a seepage of water inside the container of a Westinghouse WL 6377 ion chamber due to a lack of watertight closure. This can be attributed to corrosion of the container due to parasitic currents circulating between the container, the chamber and the reactor tank that acts as electrical ground of the system. In this work we refer over main…

Ageing ion chamber neutron flux measurement AGN-201.Settore ING-IND/20 - Misure E Strumentazione NucleariSettore ING-IND/19 - Impianti Nucleari
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