Archivio istituzionale della ricerca dell'Università degli Studi di Palermo

VELLA, Giuseppe
 Distribuzione geografica
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Continente #
NA - Nord America 5.255
EU - Europa 2.656
AS - Asia 839
AF - Africa 42
Continente sconosciuto - Info sul continente non disponibili 10
SA - Sud America 8
Totale 8.810
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Nazione #
US - Stati Uniti d'America 5.245
IT - Italia 863
UA - Ucraina 513
FI - Finlandia 467
CN - Cina 448
SG - Singapore 313
IE - Irlanda 229
DE - Germania 145
GB - Regno Unito 110
SE - Svezia 109
RU - Federazione Russa 71
FR - Francia 44
CI - Costa d'Avorio 33
KR - Corea 30
BE - Belgio 23
IR - Iran 20
RO - Romania 20
CH - Svizzera 11
CA - Canada 10
EU - Europa 10
IN - India 10
AT - Austria 8
BR - Brasile 8
NL - Olanda 8
DZ - Algeria 7
MT - Malta 7
UZ - Uzbekistan 6
GR - Grecia 5
CZ - Repubblica Ceca 4
PL - Polonia 4
LB - Libano 3
LU - Lussemburgo 3
HK - Hong Kong 2
JP - Giappone 2
LV - Lettonia 2
LY - Libia 2
MY - Malesia 2
SI - Slovenia 2
SK - Slovacchia (Repubblica Slovacca) 2
DK - Danimarca 1
ES - Italia 1
HR - Croazia 1
HU - Ungheria 1
IL - Israele 1
LT - Lituania 1
NO - Norvegia 1
SA - Arabia Saudita 1
TR - Turchia 1
Totale 8.810
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Città #
Fairfield 633
Chandler 536
Ashburn 455
Woodbridge 424
Houston 318
Wilmington 303
Ann Arbor 296
Jacksonville 282
Singapore 251
Seattle 236
Dublin 229
Cambridge 197
Palermo 159
Medford 153
Nanjing 114
Des Moines 110
Princeton 105
Tulsa 72
Helsinki 71
Boardman 60
Altamura 50
Dearborn 49
Beijing 40
Changsha 40
San Diego 36
Nanchang 34
Abidjan 33
Lawrence 33
Shenyang 32
Hebei 30
Milan 28
Seongnam 28
Verona 25
Santa Clara 24
Brussels 23
Jiaxing 23
Jinan 22
Rome 21
Falkenstein 19
Tianjin 19
Saint Petersburg 18
Ludwigshafen am Rhein 17
New York 16
Auburn Hills 14
Guangzhou 14
Venice 14
Zhengzhou 13
Ningbo 11
Kunming 10
Columbus 9
Washington 9
Pune 8
Attard 7
Hefei 6
London 6
Los Angeles 6
Munich 6
Orange 6
San Mateo 6
Vienna 6
Bologna 5
Düsseldorf 5
Lanzhou 5
Norwalk 5
Taizhou 5
Trieste 5
Zurich 5
Bagheria 4
Catania 4
Padova 4
Redmond 4
Redwood City 4
Tehran 4
Termini Imerese 4
Alcamo 3
Aversa 3
Changchun 3
Falls Church 3
Foggia 3
Genova 3
Gif-sur-yvette 3
Groningen 3
Haikou 3
Hangzhou 3
Kiev 3
Kilburn 3
Mazzano Romano 3
Moscow 3
Pembroke 3
San Francisco 3
Sandston 3
Tashkent 3
Walnut 3
Athens 2
Benghazi 2
Bratislava 2
Breganze 2
Cassino 2
Chongqing 2
Dallas 2
Totale 5.949
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Nome #
Piano di emergenza per il reattore nucleare di ricerca AGN-201 COSTANZA dell’Università di Palermo: presupposti tecnici e valutazioni radiologiche 418
A constitutive model for the thermo-mechanical behaviour of fusion-relevant pebble beds and its application to the simulation of HELICA mock-up experimental results 168
On the influence of the supporting frame on the nuclear response of the Helium-Cooled Lithium Lead Test Blanket Module for ITER 148
A neutron point kinetic model for fusion relevant calculations 148
On the nuclear response of the helium-cooled lithium lead test blanket module in ITER 147
On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material 147
On the nuclear response of the water-cooled Pb-17Li test blanket module for ITER-FEAT 146
Thermo-mechanical testing of Li-ceramic for the helium cooled pebble bed (HCPB) breeding blanket 145
Progress in the benchmark exercise for analyzing the lithiate breeder pebble bed thermo-mechanical behaviour 145
Thermal-mechanical and thermal-hydraulic integrated study of the Helium-Cooled Lithium Lead Test Blanket Module 145
Experimental tests and thermo-mechanical analyses on the HEXCALIBER mock-up 144
A study of the potential influence of frame coolant on HCLL-TBM nuclear response 142
On the numerical assessment of the thermo-mechanical performances of the DEMO Helium-Cooled Pebble Bed breeding blanket module 141
A study of the potential influence of frame coolant distribution on the radiation-induced damage of HCLL-TBM structural material 139
Steady-state and transient thermal-hydraulic analyses on ITER divertor module 138
Experimental tests on Li-ceramic breeders for the helium cooled pebble bed (HCPB) blanket design 138
On the Improved Current Pulse method for the thermal diffusive characterization of lithiated ceramic pebble beds 138
Neutronic and photonic analysis of the water-cooled Pb-17Li test blanket module for ITER-FEAT 136
Assessment of the Possible Lay-Out Influence on the HCLL-TBM Nuclear Response 135
Analyses of the OSU-MASLWR Experimental Test Facility 133
Mixed MHD convection and Tritium transport in fusion-relevant configurations 131
First Flight Escape Probability and Uncollided Flux of Nuclear Particles in Convex Bodies with Spherical Symmetry 129
A Semi-Theoretical Approach to a Correlation for the Thermal Conductivity of a Beryllium Pebble Bed 125
Sensitivity analysis of the MASLWR helical coil steam generator using TRACE 125
Study of the helium-cooled lithium lead test blanket module nuclear behaviour under irradiation in ITER 124
Steady state and transient thermal-hydraulic characterization of full-scale ITER divertor plasma facing components 123
Sensitivity Analysis of the MASLWR Helical Coil Steam Generator Using TRACE 119
Studies on the AGN - 201 "COSTANZA" Research Reactor 118
On the hyperporous non-linear elasticity model for fusion-relevant pebble beds 114
Hydraulic characterization of the full scale divertor cassette prototype 111
Analysis of a Station Black-Out transient in SMR by using the TRACE and RELAP5 code 111
Analysis Of The OSU-MASLWR-003A Natural Circulation Test By Using The TRACE Code 100
On the AGN - 201 "COSTANZA" Research Reactor at the Department of Nuclear Engineering of the University of Palermo 98
HEXCALIBER TEST SECTION. Thermo-mechanical analysis 98
A Training Experience of Operators with the AGN-201 “Costanza” Research Reactor of Palermo University 98
On the improved current pulse method for the thermal diffusive characterization of lithiated ceramic pebble beds 97
TRACE and RELAP5 Codes For Beyond Design Accident Condition Simulation in the SPES3 Facility 96
On the computational assessment of the IFMIF-EVEDA Target Assembly thermal behaviour 92
On the theoretical–numerical study of the HEXCALIBER mock-up thermo-mechanical behaviour 89
On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material 85
Analysis of Primary/Containment Coupling Phenomena Characterizing the MASLWR Design During a SBLOCA Scenario 85
ANALYSES OF TRACE-PARCS COUPLING CAPABILITY 85
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 84
Final report on the test campaigns HELICA I-II performed in HEFUS facility 83
Analysis of the Multi-Application Small Light-Water Reactor (MASLWR) design natural circulation phenomena. 83
On the use of an improved current pulse method for the experimental determination of the thermal diffusive properties of packed pebble beds 82
TRACE CODE ANALYSES FOR THE IAEA ICSP ON “INTEGRAL PWR DESIGN NATURAL CIRCULATION FLOW STABILITY AND THERMO-HYDRAULIC COUPLING OF CONTAINMENT AND PRIMARY SYSTEM DURING ACCIDENTS” 82
Post Test Analisys by Relap5 Code & Accuracy Quantification of PKLIII E3.1 Experiments (Sensitivity calculation) 81
Sezione di prova HELICA. Analisi termomeccaniche 81
Analysis, by RELAP5 code, of Boron Dilution Phenomena in a Mid-Loop Operation Transient, Performed in PKL III F2.1 RUN 1 Test 81
Post Test Analysis and Accuracy Quantification of PKL III F2.1 RUN1 Test 80
Simulazione del Circuito Primario di un Impianto Nucleare LWR Mediante L'uso Integrato Dei Codici PARCS e TRACE 78
A constitutive model for the thermo-mechanical behaviour of fusion-relevant pebble beds and its application to the simulation of HELICA mock-up experimental results 77
On the improved current pulse method for the dynamic assessment of thermal diffusive properties 77
Education and Research in Nuclear Engineering and Radiological Protection at Nuclear Engineering Department of Palermo University 77
Post Test Analysis and Accuracy Quantification of PKL III E3.1 Test 76
Applicazione del metodo Monte Carlo a problemi monodimensionali di conduzione termica stazionaria in sistemi con conducibilità dipendente dalla posizione 76
Natural Convection in Liquid Metal-Filled Rectangular Enclosures with Volumetric Heating 75
Passive safety systems in view of sustainable development 74
Environmental Radioactivity Measurements in the Mediterranean Area 73
Analisi Incidentali Deterministiche e Utilizzo di Simulatori di Impianto a Supporto delle Verifiche di Sicurezza. Sviluppo e Messa a Punto di un Modello di un Impianto PWR (EPR like) per Preliminari Analisi con il Codice TRACE di Eventi di Station Blackout 72
Analysis, by RELAP5 code, of Boron Dilution Phenomena in Small Break LOCA and in Mid Loop Operation Transients, Performed in PKL III Test Facility 71
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 71
IAEA International Collaborative Standard Problem on Integral PWR Design Natural Circulation Flow Stability and Thermo-hydraulic Coupling of Containment and Primary System during Accidents - Double Blind Calculation Results 70
Validazione e Verifica (V&V) di CATHARE2 e TRACE sul Programma Sperimentale SPES-2 70
The HELICA mock-up. Experimental results and numerical thermo-mechanical analyses 68
TRACE input model for SPES3 facility 68
A Comparison of Direct Numerical Simulation and Turbulence Models for Liquid Metal Free Convection in Volumetrically Heated Enclosures 66
Mixed MHD Convection and Tritium Transport in HCLL TBM Breeder Units for the ITER Fusion Reactor 65
Analysis of the SPES-3 direct vessel injection line break by using TRACE code 65
Adeguamento dello SPES2 per Prove di Sicurezza. Analisi Preliminari per La Simulazione di un Incidente Tipo Fukushima su SPES-2 65
Mixed magnetohydrodynamic convection in poloidal Helium-Cooled Lithium Lead blanket modules of a fusion reactor 64
Analysis, by RELAP5 code, of Boron Dilution Phenomena in a Small Break LOCA Transient, Performed in PKL III E2.2 Test 63
The hydraulic behaviour of the prototype of on a ITER divertor cassette 63
The hydraulic behaviour of the simulacrum of a Plasma Vessel Module of the W 7-X Reactor 61
ANALYSES OF THE SPES-3 DESIGN AND BEYOND DESIGN ACCIDENT CONDITION BY USING TRACE CODE 61
MHD Free Convection in Helium-Cooled Lithium-Lead Blanket Modules for the Demonstration Fusion Reactor 60
Modifiche del Codice RELAP5 per lo Studio delle Perdite di Carico in Generatori di Vapore a Tubi Elicoidali Interessati da Flussi Bifase 60
Preparation of HEXCALIBER tests and preliminary thermo-mechanical analyses 59
On the investigation of Lithium Methatitanate pebble bed thermal diffusive properties by the Improved Current Pulse method 58
The hydraulic behaviour of the ITER full-scale divertor cassette. The steady state analyses 57
The ITER divertor cassette. Steady-state characterisation and draining and drying transient hydraulic analyses 56
Out of Pile Thermo-Mechanical Testing of Breeder Pebble Beds for HCPB TBM for ITER 55
Steady state and transient thermal-hydraulic analyses on ITER divertor cassette 53
Fattibilità di una diversa configurazione della facility SPES-3 53
TRACE ANALYSIS OF THE MASLWR PRIMARY/CONTAINMENT COUPLING PHENOMENA IN BEYOND DESIGN ACCIDENT SCENARIO 52
The hydraulic behaviour of the ITER full-scale divertor cassette. The transient analyses 49
Analysis of the OSU-MASLWR Natural circulation phenomena using TRACE code 48
Analyses of TRACE-PARCS Coupling Capability 48
Analysis of a Generation 3+ Pressurised Water Reactor plant response to a postulated Station Black Out 47
Identificazione Di Componenti Di Piccola Taglia In Sistemi Di Tipo Passivo e Possibili Attività Sperimentali Per La Loro Caratterizzazione 47
Final report on the contract EFDA 682 - Preparation of integration and hydraulic tests of full-scale divertor components. 46
Implementazione ed utilizzo di simulatori semplificati “Desktop” 45
IAEA International Collaborative Standard Problem on Integral PWR Design Natural Circulation Flow Stability and Thermo-hydraulic Coupling of Containment and Primary System during Accidents 42
Analisi di Sistemi Passivi, Utilizzati in Impianti ad Acqua Pressurizzata di Tipo Avanzato. Identificazione di Componenti di Piccolo Diametro 42
Analyses Of The SPES-3 Accident Condition By Using TRACE Code 37
On the numerical assessment of the thermal-hydraulic behaviour of ITER Upper Port Plug Main Body cooling circuit 35
Analyses of the OSU-MASLWR Natural Circulation Phenomena By Using TRACE Code 28
Totale 9.054
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Categoria #
all - tutte 30.217
article - articoli 0
book - libri 0
conference - conferenze 0
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 30.217
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/20201.153 0 0 0 0 0 282 238 124 231 84 78 116
2020/20211.056 37 121 33 123 116 27 115 81 114 66 94 129
2021/2022936 39 215 3 38 36 24 29 30 115 145 35 227
2022/20231.355 164 211 47 136 169 187 98 96 160 13 43 31
2023/2024553 29 107 19 136 28 99 40 19 6 6 3 61
2024/2025546 27 100 100 135 43 141 0 0 0 0 0 0
Totale 9.054