Archivio istituzionale della ricerca dell'Università degli Studi di Palermo

VELLA, Giuseppe
 Distribuzione geografica
Salva come PNG Salva come JPEG
Continente #
NA - Nord America 7.286
EU - Europa 4.378
AS - Asia 3.124
SA - Sud America 436
Continente sconosciuto - Info sul continente non disponibili 255
AF - Africa 97
OC - Oceania 4
Totale 15.580
Salva come PNG Salva come JPEG
Nazione #
US - Stati Uniti d'America 7.158
SG - Singapore 1.119
IT - Italia 971
RU - Federazione Russa 929
CN - Cina 807
UA - Ucraina 523
FI - Finlandia 522
DE - Germania 396
BR - Brasile 329
HK - Hong Kong 319
VN - Vietnam 316
IE - Irlanda 239
PL - Polonia 206
FR - Francia 164
GB - Regno Unito 153
JP - Giappone 148
SE - Svezia 125
KR - Corea 90
CA - Canada 49
IN - India 48
BD - Bangladesh 45
CI - Costa d'Avorio 35
IQ - Iraq 30
AR - Argentina 29
MX - Messico 29
TR - Turchia 26
NL - Olanda 25
UZ - Uzbekistan 24
BE - Belgio 23
IR - Iran 22
RO - Romania 21
CO - Colombia 20
PK - Pakistan 18
DZ - Algeria 16
ID - Indonesia 16
JO - Giordania 15
SA - Arabia Saudita 15
AT - Austria 14
VE - Venezuela 14
CH - Svizzera 13
ES - Italia 12
ZA - Sudafrica 12
EC - Ecuador 11
JM - Giamaica 11
PY - Paraguay 11
EU - Europa 10
PH - Filippine 10
NP - Nepal 9
UY - Uruguay 9
IL - Israele 8
MY - Malesia 8
BO - Bolivia 7
CR - Costa Rica 7
HN - Honduras 7
MA - Marocco 7
MT - Malta 7
TN - Tunisia 6
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
BH - Bahrain 3
BY - Bielorussia 3
CL - Cile 3
GT - Guatemala 3
LU - Lussemburgo 3
PR - Porto Rico 3
SK - Slovacchia (Repubblica Slovacca) 3
SV - El Salvador 3
SY - Repubblica araba siriana 3
TT - Trinidad e Tobago 3
AL - Albania 2
BS - Bahamas 2
GD - Grenada 2
KZ - Kazakistan 2
LT - Lituania 2
LV - Lettonia 2
NI - Nicaragua 2
PE - Perù 2
SI - Slovenia 2
SN - Senegal 2
AD - Andorra 1
AE - Emirati Arabi Uniti 1
AM - Armenia 1
AO - Angola 1
BB - Barbados 1
BM - Bermuda 1
DK - Danimarca 1
DO - Repubblica Dominicana 1
EG - Egitto 1
GA - Gabon 1
GM - Gambi 1
GP - Guadalupe 1
GY - Guiana 1
Totale 15.319
Salva come PNG Salva come JPEG
Città #
Ashburn 781
Singapore 731
Fairfield 633
Chandler 536
San Jose 460
Woodbridge 424
Houston 327
Hong Kong 315
Wilmington 303
Ann Arbor 296
Jacksonville 282
Seattle 240
Dublin 239
Cambridge 197
Zgierz 195
Palermo 178
Medford 153
Tokyo 145
Council Bluffs 140
Moscow 127
Santa Clara 126
Des Moines 120
Frankfurt am Main 120
Helsinki 119
Beijing 117
Ho Chi Minh City 117
Dallas 116
Nanjing 114
Princeton 105
Munich 88
Lauterbourg 86
Hanoi 82
Tulsa 72
Boardman 64
Los Angeles 58
Milan 54
Buffalo 51
Altamura 50
Dearborn 49
Hefei 47
Changsha 40
New York 39
San Diego 37
Abidjan 35
Nanchang 34
Lawrence 33
Shenyang 33
Hebei 30
Rome 29
Seongnam 28
Tianjin 27
Chicago 26
Verona 26
Jinan 25
Jiaxing 24
Brussels 23
Orem 22
São Paulo 21
Tashkent 20
Falkenstein 19
Guangzhou 19
Paris 19
Saint Petersburg 18
Ludwigshafen am Rhein 17
Stockholm 16
Haiphong 15
Venice 15
Auburn Hills 14
Columbus 14
Zhengzhou 14
Amman 13
Brooklyn 12
Da Nang 12
Dhaka 12
Kunming 12
Phoenix 12
Rio de Janeiro 12
San Francisco 12
Washington 12
Atlanta 11
Chennai 11
City of London 11
Denver 11
London 11
Ningbo 11
Curitiba 10
Amsterdam 9
Bologna 9
Boston 9
Montreal 9
Toronto 9
Cardiff 8
Istanbul 8
Kingston 8
Montevideo 8
Philadelphia 8
Pune 8
Attard 7
Baghdad 7
Charlotte 7
Totale 9.488
Salva come PNG Salva come JPEG
Nome #
Piano di emergenza per il reattore nucleare di ricerca AGN-201 COSTANZA dell’Università di Palermo: presupposti tecnici e valutazioni radiologiche 502
Analysis of a Station Black-Out transient in SMR by using the TRACE and RELAP5 code 299
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 278
On the influence of the supporting frame on the nuclear response of the Helium-Cooled Lithium Lead Test Blanket Module for ITER 228
A study of the potential influence of frame coolant on HCLL-TBM nuclear response 227
Studies on the AGN - 201 "COSTANZA" Research Reactor 225
A neutron point kinetic model for fusion relevant calculations 224
On the nuclear response of the helium-cooled lithium lead test blanket module in ITER 217
A study of the potential influence of frame coolant distribution on the radiation-induced damage of HCLL-TBM structural material 215
Progress in the benchmark exercise for analyzing the lithiate breeder pebble bed thermo-mechanical behaviour 214
A Semi-Theoretical Approach to a Correlation for the Thermal Conductivity of a Beryllium Pebble Bed 209
On the nuclear response of the water-cooled Pb-17Li test blanket module for ITER-FEAT 209
On the Improved Current Pulse method for the thermal diffusive characterization of lithiated ceramic pebble beds 206
On the numerical assessment of the thermo-mechanical performances of the DEMO Helium-Cooled Pebble Bed breeding blanket module 206
Experimental tests and thermo-mechanical analyses on the HEXCALIBER mock-up 204
A Training Experience of Operators with the AGN-201 “Costanza” Research Reactor of Palermo University 204
Thermo-mechanical testing of Li-ceramic for the helium cooled pebble bed (HCPB) breeding blanket 203
On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material 203
Thermal-mechanical and thermal-hydraulic integrated study of the Helium-Cooled Lithium Lead Test Blanket Module 202
First Flight Escape Probability and Uncollided Flux of Nuclear Particles in Convex Bodies with Spherical Symmetry 201
Neutronic and photonic analysis of the water-cooled Pb-17Li test blanket module for ITER-FEAT 198
Mixed MHD convection and Tritium transport in fusion-relevant configurations 197
Steady-state and transient thermal-hydraulic analyses on ITER divertor module 193
Analyses of the OSU-MASLWR Experimental Test Facility 188
Assessment of the Possible Lay-Out Influence on the HCLL-TBM Nuclear Response 186
Experimental tests on Li-ceramic breeders for the helium cooled pebble bed (HCPB) blanket design 185
Sensitivity analysis of the MASLWR helical coil steam generator using TRACE 182
Sensitivity Analysis of the MASLWR Helical Coil Steam Generator Using TRACE 180
On the AGN - 201 "COSTANZA" Research Reactor at the Department of Nuclear Engineering of the University of Palermo 177
On the improved current pulse method for the thermal diffusive characterization of lithiated ceramic pebble beds 174
Steady state and transient thermal-hydraulic characterization of full-scale ITER divertor plasma facing components 172
On the hyperporous non-linear elasticity model for fusion-relevant pebble beds 170
Education and Research in Nuclear Engineering and Radiological Protection at Nuclear Engineering Department of Palermo University 168
On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material 165
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
Study of the helium-cooled lithium lead test blanket module nuclear behaviour under irradiation in ITER 164
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 164
Analysis Of The OSU-MASLWR-003A Natural Circulation Test By Using The TRACE Code 162
Sezione di prova HELICA. Analisi termomeccaniche 161
Hydraulic characterization of the full scale divertor cassette prototype 161
On the use of an improved current pulse method for the experimental determination of the thermal diffusive properties of packed pebble beds 159
Post Test Analisys by Relap5 Code & Accuracy Quantification of PKLIII E3.1 Experiments (Sensitivity calculation) 158
On the computational assessment of the IFMIF-EVEDA Target Assembly thermal behaviour 157
Analysis, by RELAP5 code, of Boron Dilution Phenomena in a Mid-Loop Operation Transient, Performed in PKL III F2.1 RUN 1 Test 154
Post Test Analysis and Accuracy Quantification of PKL III E3.1 Test 152
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 150
Final report on the test campaigns HELICA I-II performed in HEFUS facility 149
HEXCALIBER TEST SECTION. Thermo-mechanical analysis 146
Analisi Mediante Il Codice TRACE Delle Principali Fenomenologie Caratterizzanti Il Transitorio Conseguente Ad Una Rottura A Ghigliottina Nella Linea DVI dell’Impianto Sperimentale SPES-3 146
Analysis of Primary/Containment Coupling Phenomena Characterizing the MASLWR Design During a SBLOCA Scenario 145
Adeguamento dello SPES2 per Prove di Sicurezza. Analisi Preliminari per La Simulazione di un Incidente Tipo Fukushima su SPES-2 145
A Comparison of Direct Numerical Simulation and Turbulence Models for Liquid Metal Free Convection in Volumetrically Heated Enclosures 144
Passive safety systems in view of sustainable development 143
Post Test Analysis and Accuracy Quantification of PKL III F2.1 RUN1 Test 142
ANALYSES OF TRACE-PARCS COUPLING CAPABILITY 142
Analysis of the SPES-3 direct vessel injection line break by using TRACE code 141
Analysis of the Multi-Application Small Light-Water Reactor (MASLWR) design natural circulation phenomena. 140
TRACE and RELAP5 Codes For Beyond Design Accident Condition Simulation in the SPES3 Facility 140
On the improved current pulse method for the dynamic assessment of thermal diffusive properties 139
Applicazione del metodo Monte Carlo a problemi monodimensionali di conduzione termica stazionaria in sistemi con conducibilità dipendente dalla posizione 139
Environmental Radioactivity Measurements in the Mediterranean Area 139
Natural Convection in Liquid Metal-Filled Rectangular Enclosures with Volumetric Heating 139
The HELICA mock-up. Experimental results and numerical thermo-mechanical analyses 137
Analysis of a Generation 3+ Pressurised Water Reactor plant response to a postulated Station Black Out 136
Validazione e Verifica (V&V) di CATHARE2 e TRACE sul Programma Sperimentale SPES-2 134
On the theoretical–numerical study of the HEXCALIBER mock-up thermo-mechanical behaviour 132
ANALYSES OF THE SPES-3 DESIGN AND BEYOND DESIGN ACCIDENT CONDITION BY USING TRACE CODE 130
Analysis, by RELAP5 code, of Boron Dilution Phenomena in Small Break LOCA and in Mid Loop Operation Transients, Performed in PKL III Test Facility 128
On the investigation of Lithium Methatitanate pebble bed thermal diffusive properties by the Improved Current Pulse method 128
Out of Pile Thermo-Mechanical Testing of Breeder Pebble Beds for HCPB TBM for ITER 126
Simulazione del Circuito Primario di un Impianto Nucleare LWR Mediante L'uso Integrato Dei Codici PARCS e TRACE 126
Steady state and transient thermal-hydraulic analyses on ITER divertor cassette 123
Mixed magnetohydrodynamic convection in poloidal Helium-Cooled Lithium Lead blanket modules of a fusion reactor 123
Analyses Of The SPES-3 Accident Condition By Using TRACE Code 123
Modifiche del Codice RELAP5 per lo Studio delle Perdite di Carico in Generatori di Vapore a Tubi Elicoidali Interessati da Flussi Bifase 122
TRACE input model for SPES3 facility 121
Preparation of HEXCALIBER tests and preliminary thermo-mechanical analyses 120
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” 119
Analysis, by RELAP5 code, of Boron Dilution Phenomena in a Small Break LOCA Transient, Performed in PKL III E2.2 Test 118
MHD Free Convection in Helium-Cooled Lithium-Lead Blanket Modules for the Demonstration Fusion Reactor 118
The hydraulic behaviour of the simulacrum of a Plasma Vessel Module of the W 7-X Reactor 117
The hydraulic behaviour of the prototype of on a ITER divertor cassette 117
Analysis of the OSU-MASLWR Natural circulation phenomena using TRACE code 117
The hydraulic behaviour of the ITER full-scale divertor cassette. The steady state analyses 116
Fattibilità di una diversa configurazione della facility SPES-3 116
Analyses of TRACE-PARCS Coupling Capability 115
Analisi di Sistemi Passivi, Utilizzati in Impianti ad Acqua Pressurizzata di Tipo Avanzato. Identificazione di Componenti di Piccolo Diametro 114
Mixed MHD Convection and Tritium Transport in HCLL TBM Breeder Units for the ITER Fusion Reactor 113
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 111
The ITER divertor cassette. Steady-state characterisation and draining and drying transient hydraulic analyses 109
TRACE ANALYSIS OF THE MASLWR PRIMARY/CONTAINMENT COUPLING PHENOMENA IN BEYOND DESIGN ACCIDENT SCENARIO 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 104
The hydraulic behaviour of the ITER full-scale divertor cassette. The transient analyses 102
Analyses of the OSU-MASLWR Natural Circulation Phenomena By Using TRACE Code 101
Implementazione ed utilizzo di simulatori semplificati “Desktop” 95
On the numerical assessment of the thermal-hydraulic behaviour of ITER Upper Port Plug Main Body cooling circuit 93
Identificazione Di Componenti Di Piccola Taglia In Sistemi Di Tipo Passivo e Possibili Attività Sperimentali Per La Loro Caratterizzazione 89
Final report on the contract EFDA 682 - Preparation of integration and hydraulic tests of full-scale divertor components. 84
Totale 15.580
Salva come PNG Salva come JPEG
Categoria #
all - tutte 49.765
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 49.765
Salva come PNG Salva come JPEG


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2021/2022682 0 0 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
2026/2027619 220 179 220 0 0 0 0 0 0 0 0 0
Totale 15.580