Archivio istituzionale della ricerca dell'Università degli Studi di Palermo

VELLA, Giuseppe
 Distribuzione geografica
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Continente #
NA - Nord America 5.216
EU - Europa 2.540
AS - Asia 653
AF - Africa 11
Continente sconosciuto - Info sul continente non disponibili 10
SA - Sud America 8
Totale 8.438
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Nazione #
US - Stati Uniti d'America 5.206
IT - Italia 851
UA - Ucraina 513
CN - Cina 441
FI - Finlandia 399
IE - Irlanda 229
SG - Singapore 135
DE - Germania 120
GB - Regno Unito 109
SE - Svezia 109
RU - Federazione Russa 71
FR - Francia 44
KR - Corea 30
BE - Belgio 23
IR - Iran 20
RO - Romania 20
CA - Canada 10
EU - Europa 10
IN - India 10
AT - Austria 8
BR - Brasile 8
DZ - Algeria 7
MT - Malta 7
CH - Svizzera 6
UZ - Uzbekistan 6
GR - Grecia 5
CZ - Repubblica Ceca 4
PL - Polonia 4
LB - Libano 3
LU - Lussemburgo 3
NL - Olanda 3
CI - Costa d'Avorio 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
HK - Hong Kong 1
HR - Croazia 1
HU - Ungheria 1
IL - Israele 1
LT - Lituania 1
NO - Norvegia 1
SA - Arabia Saudita 1
TR - Turchia 1
Totale 8.438
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Città #
Fairfield 633
Chandler 536
Ashburn 451
Woodbridge 424
Houston 318
Wilmington 303
Ann Arbor 296
Jacksonville 282
Seattle 236
Dublin 229
Cambridge 197
Palermo 157
Medford 153
Nanjing 114
Des Moines 110
Princeton 105
Singapore 101
Tulsa 72
Boardman 60
Altamura 50
Dearborn 49
Beijing 40
Changsha 40
San Diego 36
Nanchang 34
Lawrence 33
Shenyang 32
Hebei 30
Seongnam 28
Milan 27
Verona 25
Brussels 23
Jiaxing 23
Jinan 22
Rome 21
Tianjin 19
Saint Petersburg 18
Santa Clara 18
Ludwigshafen am Rhein 17
New York 16
Auburn Hills 14
Guangzhou 14
Venice 14
Zhengzhou 13
Ningbo 11
Kunming 10
Washington 9
Pune 8
Attard 7
Hefei 6
Los Angeles 6
Orange 6
San Mateo 6
Vienna 6
Bologna 5
Düsseldorf 5
Lanzhou 5
London 5
Norwalk 5
Taizhou 5
Trieste 5
Bagheria 4
Catania 4
Padova 4
Redmond 4
Redwood City 4
Tehran 4
Alcamo 3
Aversa 3
Changchun 3
Falls Church 3
Foggia 3
Genova 3
Gif-sur-yvette 3
Haikou 3
Hangzhou 3
Helsinki 3
Kiev 3
Kilburn 3
Mazzano Romano 3
Moscow 3
Pembroke 3
San Francisco 3
Sandston 3
Tashkent 3
Walnut 3
Abidjan 2
Athens 2
Benghazi 2
Bratislava 2
Breganze 2
Chongqing 2
Dallas 2
Erice 2
Fuzhou 2
Gore 2
Hesperange 2
Hounslow 2
Imam 2
Impruneta 2
Totale 5.652
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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 416
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 165
On the nuclear response of the helium-cooled lithium lead test blanket module in ITER 145
A neutron point kinetic model for fusion relevant calculations 144
On the influence of the supporting frame on the nuclear response of the Helium-Cooled Lithium Lead Test Blanket Module for ITER 143
On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material 142
Thermal-mechanical and thermal-hydraulic integrated study of the Helium-Cooled Lithium Lead Test Blanket Module 142
On the nuclear response of the water-cooled Pb-17Li test blanket module for ITER-FEAT 142
Thermo-mechanical testing of Li-ceramic for the helium cooled pebble bed (HCPB) breeding blanket 141
Progress in the benchmark exercise for analyzing the lithiate breeder pebble bed thermo-mechanical behaviour 141
Experimental tests and thermo-mechanical analyses on the HEXCALIBER mock-up 139
On the numerical assessment of the thermo-mechanical performances of the DEMO Helium-Cooled Pebble Bed breeding blanket module 139
A study of the potential influence of frame coolant on HCLL-TBM nuclear response 138
A study of the potential influence of frame coolant distribution on the radiation-induced damage of HCLL-TBM structural material 136
Steady-state and transient thermal-hydraulic analyses on ITER divertor module 135
Experimental tests on Li-ceramic breeders for the helium cooled pebble bed (HCPB) blanket design 135
Assessment of the Possible Lay-Out Influence on the HCLL-TBM Nuclear Response 133
Neutronic and photonic analysis of the water-cooled Pb-17Li test blanket module for ITER-FEAT 132
On the Improved Current Pulse method for the thermal diffusive characterization of lithiated ceramic pebble beds 132
Mixed MHD convection and Tritium transport in fusion-relevant configurations 128
Analyses of the OSU-MASLWR Experimental Test Facility 127
First Flight Escape Probability and Uncollided Flux of Nuclear Particles in Convex Bodies with Spherical Symmetry 125
A Semi-Theoretical Approach to a Correlation for the Thermal Conductivity of a Beryllium Pebble Bed 121
Study of the helium-cooled lithium lead test blanket module nuclear behaviour under irradiation in ITER 120
Steady state and transient thermal-hydraulic characterization of full-scale ITER divertor plasma facing components 120
Sensitivity analysis of the MASLWR helical coil steam generator using TRACE 120
Studies on the AGN - 201 "COSTANZA" Research Reactor 116
Sensitivity Analysis of the MASLWR Helical Coil Steam Generator Using TRACE 115
On the hyperporous non-linear elasticity model for fusion-relevant pebble beds 109
Hydraulic characterization of the full scale divertor cassette prototype 107
Analysis Of The OSU-MASLWR-003A Natural Circulation Test By Using The TRACE Code 97
Analysis of a Station Black-Out transient in SMR by using the TRACE and RELAP5 code 96
HEXCALIBER TEST SECTION. Thermo-mechanical analysis 94
TRACE and RELAP5 Codes For Beyond Design Accident Condition Simulation in the SPES3 Facility 93
On the AGN - 201 "COSTANZA" Research Reactor at the Department of Nuclear Engineering of the University of Palermo 92
On the improved current pulse method for the thermal diffusive characterization of lithiated ceramic pebble beds 92
A Training Experience of Operators with the AGN-201 “Costanza” Research Reactor of Palermo University 92
On the theoretical–numerical study of the HEXCALIBER mock-up thermo-mechanical behaviour 86
On the computational assessment of the IFMIF-EVEDA Target Assembly thermal behaviour 82
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 82
On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material 81
Analysis of Primary/Containment Coupling Phenomena Characterizing the MASLWR Design During a SBLOCA Scenario 81
ANALYSES OF TRACE-PARCS COUPLING CAPABILITY 81
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” 81
Final report on the test campaigns HELICA I-II performed in HEFUS facility 80
Analysis of the Multi-Application Small Light-Water Reactor (MASLWR) design natural circulation phenomena. 80
On the use of an improved current pulse method for the experimental determination of the thermal diffusive properties of packed pebble beds 79
Post Test Analisys by Relap5 Code & Accuracy Quantification of PKLIII E3.1 Experiments (Sensitivity calculation) 78
Sezione di prova HELICA. Analisi termomeccaniche 78
Analysis, by RELAP5 code, of Boron Dilution Phenomena in a Mid-Loop Operation Transient, Performed in PKL III F2.1 RUN 1 Test 78
Post Test Analysis and Accuracy Quantification of PKL III F2.1 RUN1 Test 76
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 74
On the improved current pulse method for the dynamic assessment of thermal diffusive properties 73
Post Test Analysis and Accuracy Quantification of PKL III E3.1 Test 72
Simulazione del Circuito Primario di un Impianto Nucleare LWR Mediante L'uso Integrato Dei Codici PARCS e TRACE 71
Education and Research in Nuclear Engineering and Radiological Protection at Nuclear Engineering Department of Palermo University 70
Natural Convection in Liquid Metal-Filled Rectangular Enclosures with Volumetric Heating 70
Passive safety systems in view of sustainable development 69
Environmental Radioactivity Measurements in the Mediterranean Area 69
Validazione e Verifica (V&V) di CATHARE2 e TRACE sul Programma Sperimentale SPES-2 69
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 69
Applicazione del metodo Monte Carlo a problemi monodimensionali di conduzione termica stazionaria in sistemi con conducibilità dipendente dalla posizione 68
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 67
TRACE input model for SPES3 facility 67
The HELICA mock-up. Experimental results and numerical thermo-mechanical analyses 66
Analysis, by RELAP5 code, of Boron Dilution Phenomena in Small Break LOCA and in Mid Loop Operation Transients, Performed in PKL III Test Facility 65
Mixed MHD Convection and Tritium Transport in HCLL TBM Breeder Units for the ITER Fusion Reactor 63
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 63
Analysis, by RELAP5 code, of Boron Dilution Phenomena in a Small Break LOCA Transient, Performed in PKL III E2.2 Test 61
Analysis of the SPES-3 direct vessel injection line break by using TRACE code 61
Mixed magnetohydrodynamic convection in poloidal Helium-Cooled Lithium Lead blanket modules of a fusion reactor 60
The hydraulic behaviour of the prototype of on a ITER divertor cassette 60
A Comparison of Direct Numerical Simulation and Turbulence Models for Liquid Metal Free Convection in Volumetrically Heated Enclosures 60
The hydraulic behaviour of the simulacrum of a Plasma Vessel Module of the W 7-X Reactor 58
Adeguamento dello SPES2 per Prove di Sicurezza. Analisi Preliminari per La Simulazione di un Incidente Tipo Fukushima su SPES-2 58
The hydraulic behaviour of the ITER full-scale divertor cassette. The steady state analyses 56
Preparation of HEXCALIBER tests and preliminary thermo-mechanical analyses 56
ANALYSES OF THE SPES-3 DESIGN AND BEYOND DESIGN ACCIDENT CONDITION BY USING TRACE CODE 56
Modifiche del Codice RELAP5 per lo Studio delle Perdite di Carico in Generatori di Vapore a Tubi Elicoidali Interessati da Flussi Bifase 56
MHD Free Convection in Helium-Cooled Lithium-Lead Blanket Modules for the Demonstration Fusion Reactor 55
The ITER divertor cassette. Steady-state characterisation and draining and drying transient hydraulic analyses 53
Out of Pile Thermo-Mechanical Testing of Breeder Pebble Beds for HCPB TBM for ITER 52
On the investigation of Lithium Methatitanate pebble bed thermal diffusive properties by the Improved Current Pulse method 52
Steady state and transient thermal-hydraulic analyses on ITER divertor cassette 50
Fattibilità di una diversa configurazione della facility SPES-3 50
The hydraulic behaviour of the ITER full-scale divertor cassette. The transient analyses 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. 45
Implementazione ed utilizzo di simulatori semplificati “Desktop” 45
Analyses of TRACE-PARCS Coupling Capability 45
Analysis of the OSU-MASLWR Natural circulation phenomena using TRACE code 44
TRACE ANALYSIS OF THE MASLWR PRIMARY/CONTAINMENT COUPLING PHENOMENA IN BEYOND DESIGN ACCIDENT SCENARIO 44
Analysis of a Generation 3+ Pressurised Water Reactor plant response to a postulated Station Black Out 43
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 40
Analyses Of The SPES-3 Accident Condition By Using TRACE Code 35
On the numerical assessment of the thermal-hydraulic behaviour of ITER Upper Port Plug Main Body cooling circuit 33
Analyses of the OSU-MASLWR Natural Circulation Phenomena By Using TRACE Code 26
Totale 8.682
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Categoria #
all - tutte 27.920
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 27.920
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/20201.631 0 0 128 123 227 282 238 124 231 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
2024/2025174 27 100 47 0 0 0 0 0 0 0 0 0
Totale 8.682