Archivio istituzionale della ricerca dell'Università degli Studi di Palermo

VELLA, Giuseppe
 Distribuzione geografica
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Continente #
NA - Nord America 6.884
EU - Europa 4.343
AS - Asia 3.093
SA - Sud America 406
AF - Africa 97
Continente sconosciuto - Info sul continente non disponibili 11
OC - Oceania 4
Totale 14.838
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Nazione #
US - Stati Uniti d'America 6.782
SG - Singapore 1.115
IT - Italia 942
RU - Federazione Russa 929
CN - Cina 805
FI - Finlandia 522
UA - Ucraina 522
DE - Germania 396
BR - Brasile 323
HK - Hong Kong 318
VN - Vietnam 310
IE - Irlanda 239
PL - Polonia 206
FR - Francia 164
GB - Regno Unito 152
JP - Giappone 148
SE - Svezia 125
KR - Corea 90
IN - India 47
CA - Canada 41
BD - Bangladesh 39
CI - Costa d'Avorio 35
IQ - Iraq 30
MX - Messico 28
AR - Argentina 27
TR - Turchia 25
UZ - Uzbekistan 24
BE - Belgio 23
NL - Olanda 23
IR - Iran 22
RO - Romania 21
PK - Pakistan 18
DZ - Algeria 16
JO - Giordania 15
AT - Austria 14
SA - Arabia Saudita 14
ID - Indonesia 13
CH - Svizzera 12
ZA - Sudafrica 12
ES - Italia 11
PY - Paraguay 11
EU - Europa 10
JM - Giamaica 10
VE - Venezuela 10
UY - Uruguay 9
IL - Israele 8
NP - Nepal 8
PH - Filippine 8
BO - Bolivia 7
CO - Colombia 7
EC - Ecuador 7
MA - Marocco 7
MT - Malta 7
MY - Malesia 7
TN - Tunisia 6
CR - Costa Rica 5
GR - Grecia 5
KE - Kenya 5
LB - Libano 5
AU - Australia 4
AZ - Azerbaigian 4
CZ - Repubblica Ceca 4
ET - Etiopia 4
KG - Kirghizistan 4
KW - Kuwait 4
LY - Libia 4
BY - Bielorussia 3
GT - Guatemala 3
HN - Honduras 3
LU - Lussemburgo 3
SK - Slovacchia (Repubblica Slovacca) 3
SY - Repubblica araba siriana 3
TT - Trinidad e Tobago 3
AL - Albania 2
CL - Cile 2
KZ - Kazakistan 2
LT - Lituania 2
LV - Lettonia 2
NI - Nicaragua 2
PE - Perù 2
PR - Porto Rico 2
SI - Slovenia 2
SN - Senegal 2
SV - El Salvador 2
AD - Andorra 1
AE - Emirati Arabi Uniti 1
AM - Armenia 1
AO - Angola 1
BB - Barbados 1
BH - Bahrain 1
DK - Danimarca 1
DO - Repubblica Dominicana 1
EG - Egitto 1
GA - Gabon 1
GM - Gambi 1
GY - Guiana 1
HR - Croazia 1
HU - Ungheria 1
IS - Islanda 1
KH - Cambogia 1
Totale 14.827
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Città #
Ashburn 776
Singapore 729
Fairfield 633
Chandler 536
Woodbridge 424
San Jose 363
Houston 325
Hong Kong 314
Wilmington 303
Ann Arbor 296
Jacksonville 282
Dublin 239
Seattle 238
Cambridge 197
Zgierz 195
Palermo 168
Medford 153
Tokyo 145
Moscow 127
Santa Clara 123
Des Moines 120
Frankfurt am Main 120
Helsinki 119
Beijing 116
Ho Chi Minh City 115
Nanjing 114
Dallas 112
Princeton 105
Munich 88
Lauterbourg 86
Hanoi 79
Tulsa 72
Boardman 64
Los Angeles 57
Milan 52
Altamura 50
Buffalo 50
Dearborn 49
Hefei 47
Council Bluffs 45
Changsha 40
New York 37
San Diego 37
Abidjan 35
Nanchang 34
Lawrence 33
Shenyang 33
Hebei 30
Rome 29
Seongnam 28
Tianjin 27
Verona 26
Jinan 25
Jiaxing 24
Brussels 23
Orem 22
São Paulo 21
Chicago 20
Tashkent 20
Falkenstein 19
Guangzhou 19
Paris 19
Saint Petersburg 18
Ludwigshafen am Rhein 17
Stockholm 16
Venice 15
Auburn Hills 14
Columbus 14
Haiphong 14
Zhengzhou 14
Amman 13
Da Nang 12
Kunming 12
Chennai 11
City of London 11
Dhaka 11
Ningbo 11
Rio de Janeiro 11
Atlanta 10
Brooklyn 10
Curitiba 10
London 10
Washington 10
Amsterdam 9
Boston 9
San Francisco 9
Toronto 9
Bologna 8
Cardiff 8
Denver 8
Istanbul 8
Montevideo 8
Pune 8
Attard 7
Baghdad 7
Florence 7
Kingston 7
Montreal 7
Phoenix 7
Vienna 7
Totale 9.224
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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 498
Analysis of a Station Black-Out transient in SMR by using the TRACE and RELAP5 code 289
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 272
A study of the potential influence of frame coolant on HCLL-TBM nuclear response 225
On the influence of the supporting frame on the nuclear response of the Helium-Cooled Lithium Lead Test Blanket Module for ITER 223
A neutron point kinetic model for fusion relevant calculations 223
Studies on the AGN - 201 "COSTANZA" Research Reactor 221
On the nuclear response of the helium-cooled lithium lead test blanket module in ITER 214
Progress in the benchmark exercise for analyzing the lithiate breeder pebble bed thermo-mechanical behaviour 212
A study of the potential influence of frame coolant distribution on the radiation-induced damage of HCLL-TBM structural material 212
On the nuclear response of the water-cooled Pb-17Li test blanket module for ITER-FEAT 207
On the Improved Current Pulse method for the thermal diffusive characterization of lithiated ceramic pebble beds 205
A Semi-Theoretical Approach to a Correlation for the Thermal Conductivity of a Beryllium Pebble Bed 204
On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material 201
Thermo-mechanical testing of Li-ceramic for the helium cooled pebble bed (HCPB) breeding blanket 200
Thermal-mechanical and thermal-hydraulic integrated study of the Helium-Cooled Lithium Lead Test Blanket Module 200
A Training Experience of Operators with the AGN-201 “Costanza” Research Reactor of Palermo University 198
On the numerical assessment of the thermo-mechanical performances of the DEMO Helium-Cooled Pebble Bed breeding blanket module 198
First Flight Escape Probability and Uncollided Flux of Nuclear Particles in Convex Bodies with Spherical Symmetry 198
Mixed MHD convection and Tritium transport in fusion-relevant configurations 196
Experimental tests and thermo-mechanical analyses on the HEXCALIBER mock-up 196
Neutronic and photonic analysis of the water-cooled Pb-17Li test blanket module for ITER-FEAT 194
Steady-state and transient thermal-hydraulic analyses on ITER divertor module 192
Analyses of the OSU-MASLWR Experimental Test Facility 186
Assessment of the Possible Lay-Out Influence on the HCLL-TBM Nuclear Response 183
Experimental tests on Li-ceramic breeders for the helium cooled pebble bed (HCPB) blanket design 177
Sensitivity analysis of the MASLWR helical coil steam generator using TRACE 176
Sensitivity Analysis of the MASLWR Helical Coil Steam Generator Using TRACE 175
On the AGN - 201 "COSTANZA" Research Reactor at the Department of Nuclear Engineering of the University of Palermo 173
Steady state and transient thermal-hydraulic characterization of full-scale ITER divertor plasma facing components 171
On the improved current pulse method for the thermal diffusive characterization of lithiated ceramic pebble beds 168
On the hyperporous non-linear elasticity model for fusion-relevant pebble beds 167
On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material 160
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 160
Study of the helium-cooled lithium lead test blanket module nuclear behaviour under irradiation in ITER 160
Analysis Of The OSU-MASLWR-003A Natural Circulation Test By Using The TRACE Code 160
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 159
Sezione di prova HELICA. Analisi termomeccaniche 157
Education and Research in Nuclear Engineering and Radiological Protection at Nuclear Engineering Department of Palermo University 157
On the use of an improved current pulse method for the experimental determination of the thermal diffusive properties of packed pebble beds 156
Hydraulic characterization of the full scale divertor cassette prototype 156
Post Test Analisys by Relap5 Code & Accuracy Quantification of PKLIII E3.1 Experiments (Sensitivity calculation) 152
On the computational assessment of the IFMIF-EVEDA Target Assembly thermal behaviour 152
Analysis, by RELAP5 code, of Boron Dilution Phenomena in a Mid-Loop Operation Transient, Performed in PKL III F2.1 RUN 1 Test 148
Post Test Analysis and Accuracy Quantification of PKL III E3.1 Test 147
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 145
HEXCALIBER TEST SECTION. Thermo-mechanical analysis 143
Analysis of Primary/Containment Coupling Phenomena Characterizing the MASLWR Design During a SBLOCA Scenario 143
Passive safety systems in view of sustainable development 142
Adeguamento dello SPES2 per Prove di Sicurezza. Analisi Preliminari per La Simulazione di un Incidente Tipo Fukushima su SPES-2 141
ANALYSES OF TRACE-PARCS COUPLING CAPABILITY 140
Post Test Analysis and Accuracy Quantification of PKL III F2.1 RUN1 Test 139
TRACE and RELAP5 Codes For Beyond Design Accident Condition Simulation in the SPES3 Facility 139
Analisi Mediante Il Codice TRACE Delle Principali Fenomenologie Caratterizzanti Il Transitorio Conseguente Ad Una Rottura A Ghigliottina Nella Linea DVI dell’Impianto Sperimentale SPES-3 138
Final report on the test campaigns HELICA I-II performed in HEFUS facility 137
Analysis of the Multi-Application Small Light-Water Reactor (MASLWR) design natural circulation phenomena. 137
A Comparison of Direct Numerical Simulation and Turbulence Models for Liquid Metal Free Convection in Volumetrically Heated Enclosures 137
Analysis of the SPES-3 direct vessel injection line break by using TRACE code 135
Natural Convection in Liquid Metal-Filled Rectangular Enclosures with Volumetric Heating 135
Applicazione del metodo Monte Carlo a problemi monodimensionali di conduzione termica stazionaria in sistemi con conducibilità dipendente dalla posizione 133
Environmental Radioactivity Measurements in the Mediterranean Area 133
The HELICA mock-up. Experimental results and numerical thermo-mechanical analyses 128
On the theoretical–numerical study of the HEXCALIBER mock-up thermo-mechanical behaviour 128
Validazione e Verifica (V&V) di CATHARE2 e TRACE sul Programma Sperimentale SPES-2 128
On the improved current pulse method for the dynamic assessment of thermal diffusive properties 127
Analysis, by RELAP5 code, of Boron Dilution Phenomena in Small Break LOCA and in Mid Loop Operation Transients, Performed in PKL III Test Facility 124
On the investigation of Lithium Methatitanate pebble bed thermal diffusive properties by the Improved Current Pulse method 124
Analysis of a Generation 3+ Pressurised Water Reactor plant response to a postulated Station Black Out 124
Simulazione del Circuito Primario di un Impianto Nucleare LWR Mediante L'uso Integrato Dei Codici PARCS e TRACE 122
Out of Pile Thermo-Mechanical Testing of Breeder Pebble Beds for HCPB TBM for ITER 121
ANALYSES OF THE SPES-3 DESIGN AND BEYOND DESIGN ACCIDENT CONDITION BY USING TRACE CODE 120
Mixed magnetohydrodynamic convection in poloidal Helium-Cooled Lithium Lead blanket modules of a fusion reactor 118
Steady state and transient thermal-hydraulic analyses on ITER divertor cassette 117
Preparation of HEXCALIBER tests and preliminary thermo-mechanical analyses 117
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” 116
The hydraulic behaviour of the prototype of on a ITER divertor cassette 114
Analyses Of The SPES-3 Accident Condition By Using TRACE Code 114
The hydraulic behaviour of the simulacrum of a Plasma Vessel Module of the W 7-X Reactor 113
MHD Free Convection in Helium-Cooled Lithium-Lead Blanket Modules for the Demonstration Fusion Reactor 113
Modifiche del Codice RELAP5 per lo Studio delle Perdite di Carico in Generatori di Vapore a Tubi Elicoidali Interessati da Flussi Bifase 113
Analysis, by RELAP5 code, of Boron Dilution Phenomena in a Small Break LOCA Transient, Performed in PKL III E2.2 Test 112
Analysis of the OSU-MASLWR Natural circulation phenomena using TRACE code 112
TRACE input model for SPES3 facility 111
The hydraulic behaviour of the ITER full-scale divertor cassette. The steady state analyses 110
Analisi di Sistemi Passivi, Utilizzati in Impianti ad Acqua Pressurizzata di Tipo Avanzato. Identificazione di Componenti di Piccolo Diametro 110
Mixed MHD Convection and Tritium Transport in HCLL TBM Breeder Units for the ITER Fusion Reactor 109
Analyses of TRACE-PARCS Coupling Capability 107
Fattibilità di una diversa configurazione della facility SPES-3 106
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 103
The ITER divertor cassette. Steady-state characterisation and draining and drying transient hydraulic analyses 101
TRACE ANALYSIS OF THE MASLWR PRIMARY/CONTAINMENT COUPLING PHENOMENA IN BEYOND DESIGN ACCIDENT SCENARIO 101
The hydraulic behaviour of the ITER full-scale divertor cassette. The transient analyses 99
IAEA International Collaborative Standard Problem on Integral PWR Design Natural Circulation Flow Stability and Thermo-hydraulic Coupling of Containment and Primary System during Accidents 95
Analyses of the OSU-MASLWR Natural Circulation Phenomena By Using TRACE Code 93
Implementazione ed utilizzo di simulatori semplificati “Desktop” 89
On the numerical assessment of the thermal-hydraulic behaviour of ITER Upper Port Plug Main Body cooling circuit 88
Final report on the contract EFDA 682 - Preparation of integration and hydraulic tests of full-scale divertor components. 80
Identificazione Di Componenti Di Piccola Taglia In Sistemi Di Tipo Passivo e Possibili Attività Sperimentali Per La Loro Caratterizzazione 80
Totale 15.082
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Categoria #
all - tutte 47.918
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 47.918
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
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
2024/20251.535 27 100 100 135 43 158 100 123 114 138 150 347
2025/20264.918 296 160 317 267 455 724 608 593 423 859 109 107
2026/2027121 121 0 0 0 0 0 0 0 0 0 0 0
Totale 15.082