Archivio istituzionale della ricerca dell'Università degli Studi di Palermo

VELLA, Giuseppe
 Distribuzione geografica
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Continente #
NA - Nord America 6.700
EU - Europa 4.329
AS - Asia 3.090
SA - Sud America 400
AF - Africa 97
Continente sconosciuto - Info sul continente non disponibili 11
OC - Oceania 4
Totale 14.631
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Nazione #
US - Stati Uniti d'America 6.626
SG - Singapore 1.113
IT - Italia 935
RU - Federazione Russa 928
CN - Cina 805
FI - Finlandia 522
UA - Ucraina 522
DE - Germania 396
BR - Brasile 320
HK - Hong Kong 317
VN - Vietnam 310
IE - Irlanda 239
PL - Polonia 206
FR - Francia 162
GB - Regno Unito 152
JP - Giappone 148
SE - Svezia 125
KR - Corea 90
IN - India 47
BD - Bangladesh 39
CI - Costa d'Avorio 35
IQ - Iraq 30
MX - Messico 28
CA - Canada 27
AR - Argentina 26
TR - Turchia 25
UZ - Uzbekistan 24
BE - Belgio 23
NL - Olanda 23
IR - Iran 22
RO - Romania 20
PK - Pakistan 18
DZ - Algeria 16
JO - Giordania 15
SA - Arabia Saudita 14
AT - Austria 13
ID - Indonesia 13
ZA - Sudafrica 12
CH - Svizzera 11
PY - Paraguay 11
ES - Italia 10
EU - Europa 10
VE - Venezuela 10
UY - Uruguay 9
IL - Israele 8
NP - Nepal 8
PH - Filippine 8
BO - Bolivia 7
EC - Ecuador 7
JM - Giamaica 7
MA - Marocco 7
MT - Malta 7
MY - Malesia 7
CO - Colombia 6
TN - Tunisia 6
GR - Grecia 5
KE - Kenya 5
LB - Libano 5
AU - Australia 4
AZ - Azerbaigian 4
CR - Costa Rica 4
CZ - Repubblica Ceca 4
ET - Etiopia 4
KG - Kirghizistan 4
KW - Kuwait 4
LY - Libia 4
BY - Bielorussia 3
LU - Lussemburgo 3
SK - Slovacchia (Repubblica Slovacca) 3
SY - Repubblica araba siriana 3
AL - Albania 2
CL - Cile 2
GT - Guatemala 2
KZ - Kazakistan 2
LT - Lituania 2
LV - Lettonia 2
SI - Slovenia 2
SN - Senegal 2
SV - El Salvador 2
TT - Trinidad e Tobago 2
AD - Andorra 1
AE - Emirati Arabi Uniti 1
AM - Armenia 1
AO - Angola 1
BH - Bahrain 1
DK - Danimarca 1
EG - Egitto 1
GA - Gabon 1
GM - Gambi 1
GY - Guiana 1
HN - Honduras 1
HR - Croazia 1
HU - Ungheria 1
IS - Islanda 1
KH - Cambogia 1
KY - Cayman, isole 1
LK - Sri Lanka 1
MD - Moldavia 1
ME - Montenegro 1
MN - Mongolia 1
Totale 14.624
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Città #
Ashburn 774
Singapore 729
Fairfield 633
Chandler 536
Woodbridge 424
Houston 323
San Jose 315
Hong Kong 314
Wilmington 303
Ann Arbor 296
Jacksonville 282
Dublin 239
Seattle 237
Cambridge 197
Zgierz 195
Palermo 168
Medford 153
Tokyo 145
Moscow 127
Des Moines 120
Frankfurt am Main 120
Helsinki 119
Beijing 116
Ho Chi Minh City 115
Nanjing 114
Dallas 112
Santa Clara 112
Princeton 105
Munich 88
Lauterbourg 86
Hanoi 79
Tulsa 72
Boardman 64
Los Angeles 55
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
Jinan 25
Verona 25
Jiaxing 24
Brussels 23
Orem 22
São Paulo 21
Tashkent 20
Falkenstein 19
Guangzhou 19
Paris 19
Saint Petersburg 18
Chicago 17
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
Curitiba 10
London 10
Amsterdam 9
San Francisco 9
Washington 9
Bologna 8
Boston 8
Cardiff 8
Denver 8
Istanbul 8
Montevideo 8
Pune 8
Toronto 8
Atlanta 7
Attard 7
Baghdad 7
Brooklyn 7
Florence 7
Vienna 7
Warsaw 7
Duque de Caxias 6
Erbil 6
Totale 9.143
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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 494
Analysis of a Station Black-Out transient in SMR by using the TRACE and RELAP5 code 286
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 269
A study of the potential influence of frame coolant on HCLL-TBM nuclear response 224
On the influence of the supporting frame on the nuclear response of the Helium-Cooled Lithium Lead Test Blanket Module for ITER 220
A neutron point kinetic model for fusion relevant calculations 218
Studies on the AGN - 201 "COSTANZA" Research Reactor 215
On the nuclear response of the helium-cooled lithium lead test blanket module in ITER 212
Progress in the benchmark exercise for analyzing the lithiate breeder pebble bed thermo-mechanical behaviour 211
A study of the potential influence of frame coolant distribution on the radiation-induced damage of HCLL-TBM structural material 211
On the Improved Current Pulse method for the thermal diffusive characterization of lithiated ceramic pebble beds 203
On the nuclear response of the water-cooled Pb-17Li test blanket module for ITER-FEAT 202
A Semi-Theoretical Approach to a Correlation for the Thermal Conductivity of a Beryllium Pebble Bed 201
Thermo-mechanical testing of Li-ceramic for the helium cooled pebble bed (HCPB) breeding blanket 199
On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material 199
Thermal-mechanical and thermal-hydraulic integrated study of the Helium-Cooled Lithium Lead Test Blanket Module 198
A Training Experience of Operators with the AGN-201 “Costanza” Research Reactor of Palermo University 196
On the numerical assessment of the thermo-mechanical performances of the DEMO Helium-Cooled Pebble Bed breeding blanket module 196
Experimental tests and thermo-mechanical analyses on the HEXCALIBER mock-up 194
First Flight Escape Probability and Uncollided Flux of Nuclear Particles in Convex Bodies with Spherical Symmetry 193
Mixed MHD convection and Tritium transport in fusion-relevant configurations 192
Steady-state and transient thermal-hydraulic analyses on ITER divertor module 192
Neutronic and photonic analysis of the water-cooled Pb-17Li test blanket module for ITER-FEAT 191
Analyses of the OSU-MASLWR Experimental Test Facility 184
Assessment of the Possible Lay-Out Influence on the HCLL-TBM Nuclear Response 181
Sensitivity Analysis of the MASLWR Helical Coil Steam Generator Using TRACE 175
Sensitivity analysis of the MASLWR helical coil steam generator using TRACE 175
Experimental tests on Li-ceramic breeders for the helium cooled pebble bed (HCPB) blanket design 174
Steady state and transient thermal-hydraulic characterization of full-scale ITER divertor plasma facing components 170
On the AGN - 201 "COSTANZA" Research Reactor at the Department of Nuclear Engineering of the University of Palermo 169
On the improved current pulse method for the thermal diffusive characterization of lithiated ceramic pebble beds 166
On the hyperporous non-linear elasticity model for fusion-relevant pebble beds 164
Analysis Of The OSU-MASLWR-003A Natural Circulation Test By Using The TRACE Code 160
Study of the helium-cooled lithium lead test blanket module nuclear behaviour under irradiation in ITER 159
On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material 158
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 158
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 158
Sezione di prova HELICA. Analisi termomeccaniche 156
Hydraulic characterization of the full scale divertor cassette prototype 154
On the use of an improved current pulse method for the experimental determination of the thermal diffusive properties of packed pebble beds 153
Education and Research in Nuclear Engineering and Radiological Protection at Nuclear Engineering Department of Palermo University 152
Post Test Analisys by Relap5 Code & Accuracy Quantification of PKLIII E3.1 Experiments (Sensitivity calculation) 151
On the computational assessment of the IFMIF-EVEDA Target Assembly thermal behaviour 149
Analysis, by RELAP5 code, of Boron Dilution Phenomena in a Mid-Loop Operation Transient, Performed in PKL III F2.1 RUN 1 Test 147
Post Test Analysis and Accuracy Quantification of PKL III E3.1 Test 145
HEXCALIBER TEST SECTION. Thermo-mechanical analysis 142
Analysis of Primary/Containment Coupling Phenomena Characterizing the MASLWR Design During a SBLOCA Scenario 141
Passive safety systems in view of sustainable development 141
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 141
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
ANALYSES OF TRACE-PARCS COUPLING CAPABILITY 138
Adeguamento dello SPES2 per Prove di Sicurezza. Analisi Preliminari per La Simulazione di un Incidente Tipo Fukushima su SPES-2 138
Analysis of the Multi-Application Small Light-Water Reactor (MASLWR) design natural circulation phenomena. 136
A Comparison of Direct Numerical Simulation and Turbulence Models for Liquid Metal Free Convection in Volumetrically Heated Enclosures 136
Final report on the test campaigns HELICA I-II performed in HEFUS facility 134
Analysis of the SPES-3 direct vessel injection line break by using TRACE code 134
Natural Convection in Liquid Metal-Filled Rectangular Enclosures with Volumetric Heating 134
Analisi Mediante Il Codice TRACE Delle Principali Fenomenologie Caratterizzanti Il Transitorio Conseguente Ad Una Rottura A Ghigliottina Nella Linea DVI dell’Impianto Sperimentale SPES-3 134
Applicazione del metodo Monte Carlo a problemi monodimensionali di conduzione termica stazionaria in sistemi con conducibilità dipendente dalla posizione 132
Environmental Radioactivity Measurements in the Mediterranean Area 131
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
On the improved current pulse method for the dynamic assessment of thermal diffusive properties 125
Validazione e Verifica (V&V) di CATHARE2 e TRACE sul Programma Sperimentale SPES-2 124
Analysis, by RELAP5 code, of Boron Dilution Phenomena in Small Break LOCA and in Mid Loop Operation Transients, Performed in PKL III Test Facility 123
Simulazione del Circuito Primario di un Impianto Nucleare LWR Mediante L'uso Integrato Dei Codici PARCS e TRACE 122
On the investigation of Lithium Methatitanate pebble bed thermal diffusive properties by the Improved Current Pulse method 121
Analysis of a Generation 3+ Pressurised Water Reactor plant response to a postulated Station Black Out 121
Out of Pile Thermo-Mechanical Testing of Breeder Pebble Beds for HCPB TBM for ITER 120
Mixed magnetohydrodynamic convection in poloidal Helium-Cooled Lithium Lead blanket modules of a fusion reactor 117
ANALYSES OF THE SPES-3 DESIGN AND BEYOND DESIGN ACCIDENT CONDITION BY USING TRACE CODE 117
Preparation of HEXCALIBER tests and preliminary thermo-mechanical analyses 116
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” 115
The hydraulic behaviour of the prototype of on a ITER divertor cassette 113
Analysis, by RELAP5 code, of Boron Dilution Phenomena in a Small Break LOCA Transient, Performed in PKL III E2.2 Test 111
Modifiche del Codice RELAP5 per lo Studio delle Perdite di Carico in Generatori di Vapore a Tubi Elicoidali Interessati da Flussi Bifase 111
The hydraulic behaviour of the simulacrum of a Plasma Vessel Module of the W 7-X Reactor 110
Analysis of the OSU-MASLWR Natural circulation phenomena using TRACE code 110
TRACE input model for SPES3 facility 110
Analyses Of The SPES-3 Accident Condition By Using TRACE Code 110
The hydraulic behaviour of the ITER full-scale divertor cassette. The steady state analyses 109
Steady state and transient thermal-hydraulic analyses on ITER divertor cassette 108
MHD Free Convection in Helium-Cooled Lithium-Lead Blanket Modules for the Demonstration Fusion Reactor 108
Mixed MHD Convection and Tritium Transport in HCLL TBM Breeder Units for the ITER Fusion Reactor 107
Analyses of TRACE-PARCS Coupling Capability 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
Analisi di Sistemi Passivi, Utilizzati in Impianti ad Acqua Pressurizzata di Tipo Avanzato. Identificazione di Componenti di Piccolo Diametro 103
Fattibilità di una diversa configurazione della facility SPES-3 102
TRACE ANALYSIS OF THE MASLWR PRIMARY/CONTAINMENT COUPLING PHENOMENA IN BEYOND DESIGN ACCIDENT SCENARIO 100
The ITER divertor cassette. Steady-state characterisation and draining and drying transient hydraulic analyses 99
The hydraulic behaviour of the ITER full-scale divertor cassette. The transient analyses 98
IAEA International Collaborative Standard Problem on Integral PWR Design Natural Circulation Flow Stability and Thermo-hydraulic Coupling of Containment and Primary System during Accidents 94
Analyses of the OSU-MASLWR Natural Circulation Phenomena By Using TRACE Code 90
On the numerical assessment of the thermal-hydraulic behaviour of ITER Upper Port Plug Main Body cooling circuit 87
Implementazione ed utilizzo di simulatori semplificati “Desktop” 86
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 79
Totale 14.875
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Categoria #
all - tutte 46.857
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 46.857
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021129 0 0 0 0 0 0 0 0 0 0 0 129
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
2024/20251.535 27 100 100 135 43 158 100 123 114 138 150 347
2025/20264.832 296 160 317 267 455 724 608 593 423 859 109 21
Totale 14.875