Archivio istituzionale della ricerca dell'Università degli Studi di Palermo

CHIOVARO, Pierluigi
 Distribuzione geografica
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Continente #
NA - Nord America 5.205
EU - Europa 3.132
AS - Asia 2.443
SA - Sud America 318
AF - Africa 60
OC - Oceania 6
Continente sconosciuto - Info sul continente non disponibili 2
Totale 11.166
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Nazione #
US - Stati Uniti d'America 5.138
RU - Federazione Russa 901
SG - Singapore 892
IT - Italia 718
CN - Cina 641
FI - Finlandia 302
VN - Vietnam 264
BR - Brasile 258
DE - Germania 258
HK - Hong Kong 246
UA - Ucraina 206
PL - Polonia 173
FR - Francia 123
IE - Irlanda 120
GB - Regno Unito 110
JP - Giappone 84
IN - India 49
SE - Svezia 47
BD - Bangladesh 46
KR - Corea 45
NL - Olanda 33
CA - Canada 28
IQ - Iraq 28
AR - Argentina 22
MX - Messico 21
BE - Belgio 19
PK - Pakistan 19
ES - Italia 16
AT - Austria 15
CH - Svizzera 15
ID - Indonesia 15
TR - Turchia 14
CI - Costa d'Avorio 12
JO - Giordania 12
RO - Romania 12
UZ - Uzbekistan 12
GR - Grecia 11
ZA - Sudafrica 11
PH - Filippine 10
SA - Arabia Saudita 9
DZ - Algeria 8
EC - Ecuador 8
MA - Marocco 8
MT - Malta 8
VE - Venezuela 8
CO - Colombia 7
AL - Albania 6
AU - Australia 6
MY - Malesia 6
BY - Bielorussia 5
CR - Costa Rica 5
JM - Giamaica 5
KE - Kenya 5
LB - Libano 5
LT - Lituania 5
NP - Nepal 5
SI - Slovenia 5
AZ - Azerbaigian 4
CZ - Repubblica Ceca 4
OM - Oman 4
PT - Portogallo 4
PY - Paraguay 4
TN - Tunisia 4
UY - Uruguay 4
AE - Emirati Arabi Uniti 3
CL - Cile 3
EG - Egitto 3
IL - Israele 3
IR - Iran 3
KW - Kuwait 3
KZ - Kazakistan 3
MM - Myanmar 3
PE - Perù 3
TT - Trinidad e Tobago 3
DK - Danimarca 2
ET - Etiopia 2
GE - Georgia 2
GT - Guatemala 2
HR - Croazia 2
KG - Kirghizistan 2
MD - Moldavia 2
PS - Palestinian Territory 2
RS - Serbia 2
SK - Slovacchia (Repubblica Slovacca) 2
SN - Senegal 2
SY - Repubblica araba siriana 2
TW - Taiwan 2
A2 - ???statistics.table.value.countryCode.A2??? 1
AD - Andorra 1
AG - Antigua e Barbuda 1
AM - Armenia 1
BA - Bosnia-Erzegovina 1
BG - Bulgaria 1
BH - Bahrain 1
BO - Bolivia 1
DO - Repubblica Dominicana 1
EE - Estonia 1
GM - Gambi 1
GN - Guinea 1
IS - Islanda 1
Totale 11.157
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Città #
Ashburn 628
Singapore 570
Fairfield 556
Chandler 409
Houston 289
Woodbridge 287
San Jose 261
Wilmington 241
Hong Kong 240
Seattle 227
Cambridge 210
Ann Arbor 189
Palermo 179
Zgierz 151
Beijing 129
Dublin 116
Des Moines 114
Munich 102
Moscow 101
Ho Chi Minh City 97
Medford 92
Jacksonville 84
Tokyo 78
Los Angeles 75
Dallas 74
Helsinki 74
Lauterbourg 67
Santa Clara 65
Princeton 64
Hanoi 60
Altamura 57
Council Bluffs 56
Frankfurt am Main 56
Nanjing 55
New York 52
Rome 46
Hefei 45
Dearborn 39
Milan 37
San Diego 37
Buffalo 36
Lawrence 35
Boardman 31
Changsha 27
Tulsa 26
Chicago 23
Shenyang 22
São Paulo 20
Jinan 19
London 19
Venice 19
Amsterdam 18
Brussels 17
Ludwigshafen am Rhein 17
Nanchang 17
Orem 17
Warsaw 17
Guangzhou 16
Atlanta 14
Baghdad 14
Jiaxing 14
Chennai 13
Da Nang 13
Lappeenranta 13
Seongnam 13
Abidjan 12
Saint Petersburg 12
Norwalk 11
Pune 11
Tianjin 11
Zurich 11
Amman 10
Columbus 10
Ningbo 10
Bologna 9
Hebei 9
Nuremberg 9
Paris 9
Zhengzhou 9
Dhaka 8
Falkenstein 8
Haiphong 8
Hangzhou 8
Johannesburg 8
Phoenix 8
Redmond 8
Rio de Janeiro 8
San Paolo di Civitate 8
Tashkent 8
Turin 8
Attard 7
Curitiba 7
Denver 7
Naples 7
Redondo Beach 7
San Francisco 7
Stockholm 7
Verona 7
Washington 7
Auburn Hills 6
Totale 7.099
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Nome #
On the thermo-mechanical behaviour of DEMO water-cooled lithium lead equatorial outboard blanket module 337
Analysis of a Station Black-Out transient in SMR by using the TRACE and RELAP5 code 286
Analysis of the thermo-mechanical behaviour of the DEMO Water-Cooled Lithium Lead breeding blanket module under normal operation steady state conditions 256
A study of the potential influence of frame coolant on HCLL-TBM nuclear response 223
On the influence of the supporting frame on the nuclear response of the Helium-Cooled Lithium Lead Test Blanket Module for ITER 219
A neutron point kinetic model for fusion relevant calculations 218
On the nuclear response of the helium-cooled lithium lead test blanket module in ITER 212
Studies on the AGN - 201 "COSTANZA" Research Reactor 211
A study of the potential influence of frame coolant distribution on the radiation-induced damage of HCLL-TBM structural material 211
On the nuclear response of the water-cooled Pb-17Li test blanket module for ITER-FEAT 200
On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material 198
Thermal-mechanical and thermal-hydraulic integrated study of the Helium-Cooled Lithium Lead Test Blanket Module 197
On the numerical assessment of the thermo-mechanical performances of the DEMO Helium-Cooled Pebble Bed breeding blanket module 195
A multi-physics integrated approach to breeding blanket modelling and design 195
A Training Experience of Operators with the AGN-201 “Costanza” Research Reactor of Palermo University 194
First Flight Escape Probability and Uncollided Flux of Nuclear Particles in Convex Bodies with Spherical Symmetry 193
Neutronic and photonic analysis of the water-cooled Pb-17Li test blanket module for ITER-FEAT 191
On the optimization of the first wall of the DEMO water-cooled lithium lead outboard breeding blanket equatorial module 184
Assessment of the Possible Lay-Out Influence on the HCLL-TBM Nuclear Response 181
Probabilità di fuga di "particelle" nucleari da corpi a simmetria sferica 181
Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System 181
Multi-Module vs. Single-Module concept: Comparison of thermomechanical performances for the DEMO Water-Cooled Lithium Lead breeding blanket 175
Nuclear Analysis of an ITER Blanket Module 171
On the AGN - 201 "COSTANZA" Research Reactor at the Department of Nuclear Engineering of the University of Palermo 169
On the adoption of the Monte Carlo method to solve one-dimensional steady state thermal diffusion problems for non-uniform solids 164
Optimization of the breeder zone cooling tubes of the DEMO Water-Cooled Lithium Lead breeding blanket 161
Study of the helium-cooled lithium lead test blanket module nuclear behaviour under irradiation in ITER 159
Validation of Multi-Physics Integrated Procedure for the HCPB Breeding Blanket 159
On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material 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
Numerical assessment of the thermomechanical behaviour of the DEMO Water-Cooled Lithium Lead inboard blanket equatorial module 154
Education and Research in Nuclear Engineering and Radiological Protection at Nuclear Engineering Department of Palermo University 152
Analysis of the thermo-mechanical behaviour of the DEMO Water-Cooled Lithium Lead breeding blanket module under normal operation steady state conditions 148
Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project 148
Investigation of the DEMO WCLL Breeding Blanket Cooling Water Activation 148
Assessment of the importance of neutron multiplication for tritium production 147
Assessment of the Thermo-mechanical Performances of a DEMO Water-Cooled Liquid Metal Blanket Module 147
Hypothetical porous medium concept as a virtual swirl tape: A novel modelling technique towards efficient CFD simulation of swirl tape cooling pipe 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
Adeguamento dello SPES2 per Prove di Sicurezza. Analisi Preliminari per La Simulazione di un Incidente Tipo Fukushima su SPES-2 137
Structural analysis of the back supporting structure of the DEMO WCLL outboard blanket 137
Production and transport modelling of Po-210 in DEMO reactor 134
Analysis of the SPES-3 direct vessel injection line break by using TRACE code 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
Integrated design of breeding blanket and ancillary systems related to the use of helium or water as a coolant and impact on the overall plant design 132
Structural assessment of the EU-DEMO WCLL Central Outboard Blanket segment under normal and off-normal operating conditions 128
A Monte Carlo study on the possible lay-out influence in the HCLL-TBM nuclear response 127
On the improved current pulse method for the dynamic assessment of thermal diffusive properties 125
Preliminary thermo-mechanical assessment of the Top Cap region of the Water-Cooled Lead-Ceramic Breeder Breeding Blanket alternative concept 124
Numerical structural analysis and flow-induced vibration study in support of the design of the EU-DEMO once-through steam generator mock-up for the STEAM experimental facility 123
Validazione e Verifica (V&V) di CATHARE2 e TRACE sul Programma Sperimentale SPES-2 122
Analysis of a Generation 3+ Pressurised Water Reactor plant response to a postulated Station Black Out 121
Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems 118
ANALYSES OF THE SPES-3 DESIGN AND BEYOND DESIGN ACCIDENT CONDITION BY USING TRACE CODE 117
Una variante del problema dell'ago di Buffon e verifica con il metodo Monte Carlo 116
Assessment of DEMO WCLL breeding blanket primary heat transfer system isolation valve absorbed doses due to activated water 113
Modifiche del Codice RELAP5 per lo Studio delle Perdite di Carico in Generatori di Vapore a Tubi Elicoidali Interessati da Flussi Bifase 110
TRACE input model for SPES3 facility 108
Parametric study of the influence of First Wall cooling water on the Water Cooled Lithium Lead Breeding Blanket nuclear response 106
Sul numero delle disposizioni delle N parti dell'intero M nel caso in cui nessuna delle parti possa essere superiore a Q 105
On the modelling of tritium transport phenomena at fluid-structure interfaces 104
Fattibilità di una diversa configurazione della facility SPES-3 102
Thermal-hydraulic study of the Primary Heat Transport System of the DEMO Divertor Cassette Body 100
Thermomechanical and Thermofluid-Dynamic Coupled Analysis of the Top Cap Region of the Water-Cooled Lithium Lead Breeding Blanket for the EU DEMO Fusion Reactor 99
Multiphysics Optimization for First Wall Design Enhancement in Water-Cooled Breeding Blankets 98
Activated corrosion product contamination assessments of DEMO WCLL breeding blanket primary heat transport system 90
Development and application of an alternative modelling approach for the thermo-mechanical analysis of a DEMO water-cooled lithium lead breeding blanket segment 90
Numerical investigation of the structural performances of the EU-DEMO Water-Cooled Lead Lithium breeding blanket equipped with helicoidal double-walled tubes 89
Embrittlement of WCLL blanket and its fracture mechanical assessment 87
Implementazione ed utilizzo di simulatori semplificati “Desktop” 85
Water activation products generation and transport in DEMO divertor 82
Thermal–hydraulic study of the Primary Heat Transport System of the EU-DEMO Divertor Plasma Facing Components 80
Thermofluid-dynamic and thermal–structural assessment of the EU-DEMO WCLL “double bundle” Breeding Blanket concept left outboard segment 78
Thermal and structural analysis of the European water-cooled lithium lead breeding blanket concept in the L-H mode transition 76
null 70
Feasibility of D-D start-up under realistic technological assumptions for EU-DEMO 62
Exploratory thermal and fluid-dynamic assessment of a pin of the Helium cooled pebble bed breeding blanket concept with a modular pin monoblock design for the EU DEMO nuclear fusion reactor 45
Exploratory thermo-mechanical assessment of a pin of the Helium Cooled Pebble Bed breeding blanket concept with a modular pin monoblock design for the EU DEMO nuclear fusion reactor 43
Thermofluid-dynamic assessment of the dual cooling scheme EU-DEMO divertor cassette 41
Coolant contamination in gas-cooled reactors due to neutronic sputtering 38
Totale 11.525
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Categoria #
all - tutte 39.602
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 39.602
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021128 0 0 0 0 0 0 0 0 0 0 55 73
2021/2022705 38 107 12 22 21 43 70 31 86 97 37 141
2022/20231.104 104 207 24 110 109 150 126 88 116 13 31 26
2023/2024504 27 70 24 93 34 81 55 28 12 18 3 59
2024/20251.457 13 115 104 91 41 147 159 111 101 114 160 301
2025/20264.265 299 145 306 244 423 686 661 561 328 489 123 0
Totale 11.525