0000000001185429
AUTHOR
Mariarosa Giardina
Misure spettrometriche gamma di concentrazioni radionuclidiche in campioni ambientali e alimentari in situazioni di emergenza
Uso integrato di metodologie FMEA, HAZOP e FAULT TREE nella windowless target unit di un Accelerator Driven System
FUZZY RISK ANALYSIS OF A MODERN γ-RAY INDUSTRIAL IRRADIATOR
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…
Safety studies of a hydrogen refuelling station: Determination of the occurrence frequency of the accidental scenarios
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…
A semi-empirical approach for predicting two-phase flow discharge through branches of various orientations connected to a horizontal main pipe
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…
A Review of Healthcare Failure Mode and Effects Analysis (HFMEA) in Radiotherapy
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.
Analysis of operator human errors in hydrogen refuelling stations: Comparison between human rate assessment techniques
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…
Analysis of Protected Accidental Transients in the EFIT Reactor With the RELAP5 Thermal-Hydraulic Code
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 …
THERP and HEART integrated methodology for human error assessment
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…
Modifiche al codice RELAP5 per l’analisi termofluidodinamica monofase delle perdite di carico in scambiatori di calore a tubi elicoidali
Rewetting of a hot vertical surface by liquid sprays
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 …
ICONE19-43144 RELAP5 SIMULATION OF TWO-PHASE FLOW EXPERIMENTS IN VERTICAL HELICAL TUBES
Atmospheric dry deposition processes of particles on urban and suburban surfaces: Modelling and validation works
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…
Prediction of the heat exchange in MEGAPIE facility by using RELAP5 code
RPN safety analysis to reduce the risk of malpractices in high dose rate brachytherapy
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…
A new approach for modeling dry deposition velocity of particles
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…
Analisi di sicurezza e valutazione dell’errore umano nelle procedure di manutenzione del sistema di stoccaggio in un autobus a metano
On the numerical assessment of the thermal-hydraulic operating map of the DEMO Divertor Plasma Facing Components cooling circuit
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 …
Analysis of radionuclide concentration in air released through the stack of a radiopharmaceutical production facility based on a medical cyclotron
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…
Early-design improvement of human reliability in an experimental facility: A combined approach and application on SPES
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 (…
FMECA Application in Tomotherapy: Comparison between Classic and Fuzzy Methodologies
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. …
Fuzzy environmental analogy index to develop environmental similarity maps for designing air quality monitoring networks on a large-scale
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…
Fuzzy fault tree analysis in modern γ-ray industrial irradiator: Use of fuzzy version of HEART and CREAM techniques for human error evaluation
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…
Thermal-hydraulic analysis on the cooling system of the target in the SPES plant
RELAP5 Modification for CHEOPE Simulations
A new tool to process forecast meteorological data for atmospheric pollution dispersion simulations of accident scenarios: A Sicily-based case study
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…
Risk analysis using fuzzy set theory of accidental exposure of medical staff during brachytherapy procedures
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…
Modifiche del Codice RELAP5 per lo Studio delle Perdite di Carico in Generatori di Vapore a Tubi Elicoidali Interessati da Flussi Bifase
MELCOR per lo Studio Integrale di Sequenze Incidentali su Reattori PWR da 900 MWe e valutazioni preliminari d'impatto a breve e medio raggio
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 …
TRACE input model for SPES3 facility
Esposizione potenziale in impianti di irraggiamento: un’analisi mediante probabilità di tipo sfumato
Studies of thermalfluid-dynamic phenomenologies in high energy industrial systems during accidental transients
The TREEZZY2 Computer Code for Fault Tree and Event Tree Analyses with Fuzzy Probabilities
Studio della sicurezza di una stazione di rifornimento di idrogeno per autotrazione mediante l’uso integrato di tecniche di analisi di rischio
Pre-conceptual design of EU-DEMO Divertor primary heat transfer systems
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…
Thermalhydraulic analyses of overpower transients in the EFIT reactor
Qualifica di codici di calcolo dedicati alle analisi di sistema avanzati quando applicati nella simulazione di impianti a metallo liquido
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
Safety study of an LNG regasification plant using an FMECA and HAZOP integrated methodology
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 …
THERP and HEART integrated methodology for human error assessment
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.
Applicazione della tecnica HFMEA in radioterapia
Studi di sicurezza con metodologie ad albero di guasti riguardanti l’esposizione potenziale di un operatore in un reparto di brachiterapia
Analysis of radionuclide concentration in air released through the stack of a radiopharmaceutical production facility
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…
Analisi Mediante Il Codice TRACE Delle Principali Fenomenologie Caratterizzanti Il Transitorio Conseguente Ad Una Rottura A Ghigliottina Nella Linea DVI dell’Impianto Sperimentale SPES-3
FMECA Analyses of radiological over-exposure accident to patients in brachytherapy
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.
Fuzzy FMECA analysis of radioactive gas recovery system in the SPES experimental facility
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…
RELAP5 simulation of two-phase flow experiments in vertical helical tubes
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…
Esposizione potenziale dell’operatore in un impianto dotato di acceleratore: studio mediante l’uso di tecniche ad albero di guasto di tipo sfumato
Analyses of single- and two-phase flow pressure drops in helical pipes using a modified RELAP5 code
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…
Decay Heat Removal and Transient Analysis in Accidental Conditions in the EFIT Reactor
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…
Modifiche del codice RELAP5/MOD3.2.b per lo studio delle perdite di carico e dello scambio termico in condotti elicoidali interessati da deflussi bifase: validazione attraverso gli esperimenti effettuati dal Politecnico di Milano presso l’impianto SIET di Piacenza
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…
Analisi di sicurezza mediante l’uso di tecniche ad alberi di guasto FUZZY dell’impianto nucleare dimostrativo XADS
Linguistic Approach to Support Human Reliability Analysis and Validation Work in Advanced Radiotherapy Technologies
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…
Fuzzy risk analysis of a modern gamma-ray industrial irradiator
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…
Education and Research in Nuclear Engineering and Radiological Protection at Nuclear Engineering Department of Palermo University
Thermal hydraulic analyses in the windowless target of an Accelerator Driven System
Dry deposition of particle on urban areas
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 …
SAFETY ANALYSES OF POTENTIAL EXPOSURE IN MEDICAL IRRADIATION PLANTS BY FUZZY FAULT TREE
Valutazione della dose potenziale per alcuni scenari incidentali in un impianto HDR: uso di tecniche di tipo sfumato
A Training Experience of Operators with the AGN-201 “Costanza” Research Reactor of Palermo University
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 …
Analisi di sicurezza nella procedura di protonterapia oculare applicata presso i Laboratori del Sud dell’INFN di Catania
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…
Dry deposition models for radionuclides dispersed in air: a new approach for deposition velocity evaluation schema
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…
Human Reliability Analysis to support operational planning of an experimental facility
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…
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 paziente in brachiterapia
Multiple failure accidental transients in the LBE-XADS
Analisi di sicurezza integrata e ricorsiva per l’impianto nucleare dimostrativo XADS
New Implementations in RELAP5 for Post-Test Analysis of the MEGAPIE Irradiation Phase
Predicting two-phase flow discharge through branches of various orientation connected to a horizontal main pipe
Fuzzy modelling of HEART methodology: application in safety analyses of accidental exposure in irradiation plants
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…
Modifying RELAP5 code to deal with helical coiled ducts
Rewetting by liquid spray of a hot metallic wall
Risk assessment of component failure modes and human errors using a new FMECA approach: application in the safety analysis of HDR brachytherapy
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…
Flowblockage failures in the EFIT reactor
Recent improvement of RELAP5 as numerical tool for interpretation of thermal-hydraulic experiments
Safety analysis in the LBE-Cooled XADS plant through an integrated use of HAZOP, FAULT TREE and thermalhydraulic transient analyses
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…
Dividing two-phase flow in branching conduits with large diameter horizontal main pipes and lateral branches
RELAP5-3D thermal hydraulic analysis of the target cooling system in the SPES experimental facility
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 …
Thermalhydraulic analyses of overpower transients without proton beam trip in the XADS facility
Analisi di sicurezza di una stazione di rifornimento di idrogeno per autotrazione:uso delle tecniche FMEA e HAZOP
Studio con il codice RELAP5 delle perdite di carico e dello scambio termico in tubi elicoidali interessati da deflussi monofase
Verification of the RELAP5 code against the MEGAPIE irradiation experiment
RELAP5 simulations for CIRCE experiments
PROVE ED ESPERIMENTI DI VERIFICA DELLA SICUREZZA DEL REATTORE NUCLEARE DI RICERCA AGN-201 “COSTANZA”
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.
TREEZZY2, a Fuzzy Logic Computer Code for Fault Tree and Event Tree Analyses
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…
Risk analysis of the storage unit in a hydrogen refuelling station
Uso di formulazioni della metodologia cream per la trattazione dell’errore umano nella valutazione ad alberi di guasto della probabilita’ di esposizione di un operatore in un impianto di irraggiamento gamma
Maintenance Operation on AGN-201 “COSTANZA” Nuclear Research Reactor of Palermo University
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…