Archivio istituzionale della ricerca dell'Università degli Studi di Palermo

CHIOVARO, Pierluigi
 Distribuzione geografica
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Continente #
NA - Nord America 6.262
EU - Europa 3.259
AS - Asia 2.532
SA - Sud America 379
Continente sconosciuto - Info sul continente non disponibili 362
AF - Africa 63
OC - Oceania 6
Totale 12.863
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Nazione #
US - Stati Uniti d'America 6.122
RU - Federazione Russa 902
SG - Singapore 897
IT - Italia 799
CN - Cina 649
FI - Finlandia 302
BR - Brasile 280
VN - Vietnam 266
DE - Germania 261
HK - Hong Kong 253
UA - Ucraina 209
PL - Polonia 173
FR - Francia 129
GB - Regno Unito 127
IE - Irlanda 120
JP - Giappone 89
BD - Bangladesh 80
CA - Canada 55
IN - India 50
SE - Svezia 47
KR - Corea 45
NL - Olanda 35
MX - Messico 31
AR - Argentina 28
IQ - Iraq 28
CO - Colombia 23
ID - Indonesia 21
BE - Belgio 20
PK - Pakistan 19
ES - Italia 18
TR - Turchia 17
CH - Svizzera 16
CR - Costa Rica 16
AT - Austria 15
EC - Ecuador 14
JM - Giamaica 14
VE - Venezuela 14
CI - Costa d'Avorio 13
PH - Filippine 13
RO - Romania 13
SA - Arabia Saudita 13
JO - Giordania 12
UZ - Uzbekistan 12
GR - Grecia 11
MY - Malesia 11
ZA - Sudafrica 11
DZ - Algeria 8
MA - Marocco 8
MT - Malta 8
NP - Nepal 7
AL - Albania 6
AU - Australia 6
EE - Estonia 6
KE - Kenya 6
LT - Lituania 6
BY - Bielorussia 5
CL - Cile 5
CZ - Repubblica Ceca 5
LB - Libano 5
SI - Slovenia 5
TT - Trinidad e Tobago 5
UY - Uruguay 5
AZ - Azerbaigian 4
OM - Oman 4
PE - Perù 4
PT - Portogallo 4
PY - Paraguay 4
SV - El Salvador 4
TN - Tunisia 4
AE - Emirati Arabi Uniti 3
BH - Bahrain 3
BS - Bahamas 3
DO - Repubblica Dominicana 3
EG - Egitto 3
GT - Guatemala 3
IL - Israele 3
IR - Iran 3
KW - Kuwait 3
KZ - Kazakistan 3
MM - Myanmar 3
PS - Palestinian Territory 3
BO - Bolivia 2
DK - Danimarca 2
ET - Etiopia 2
GE - Georgia 2
HN - Honduras 2
HR - Croazia 2
HU - Ungheria 2
KG - Kirghizistan 2
MD - Moldavia 2
RS - Serbia 2
SK - Slovacchia (Repubblica Slovacca) 2
SN - Senegal 2
SY - Repubblica araba siriana 2
TH - Thailandia 2
TW - Taiwan 2
XK - ???statistics.table.value.countryCode.XK??? 2
A2 - ???statistics.table.value.countryCode.A2??? 1
AD - Andorra 1
AG - Antigua e Barbuda 1
Totale 12.488
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Città #
Ashburn 680
Singapore 573
Fairfield 556
San Jose 477
Chandler 411
Houston 295
Woodbridge 287
Hong Kong 245
Wilmington 242
Seattle 231
Cambridge 210
Palermo 197
Ann Arbor 189
Zgierz 151
Beijing 131
Dublin 116
Des Moines 114
Council Bluffs 102
Munich 102
Moscow 101
Ho Chi Minh City 98
Medford 92
Jacksonville 87
Dallas 84
Santa Clara 84
Tokyo 81
Los Angeles 79
Helsinki 74
Lauterbourg 67
New York 65
Princeton 64
Hanoi 60
Frankfurt am Main 58
Altamura 57
Nanjing 55
Boardman 54
Rome 50
Hefei 45
Chicago 44
Dearborn 40
Milan 40
Buffalo 38
San Diego 37
Lawrence 35
San Marcos 29
Changsha 27
Tulsa 27
Shenyang 22
São Paulo 22
Atlanta 20
Jinan 19
London 19
Venice 19
Amsterdam 18
Brussels 17
Ludwigshafen am Rhein 17
Nanchang 17
Orem 17
Warsaw 17
Guangzhou 16
Phoenix 16
Baghdad 14
Jiaxing 14
Abidjan 13
Chennai 13
Columbus 13
Da Nang 13
Lappeenranta 13
Seongnam 13
Brooklyn 12
Denver 12
Philadelphia 12
Saint Petersburg 12
Toronto 12
Washington 12
Bologna 11
Norwalk 11
Pune 11
Tianjin 11
Turin 11
Zurich 11
Amman 10
Memphis 10
Naples 10
Ningbo 10
Dhaka 9
Haiphong 9
Hattiesburg 9
Hebei 9
Miami 9
Nuremberg 9
Paris 9
Rio de Janeiro 9
San Francisco 9
San José 9
Verona 9
Zhengzhou 9
Falkenstein 8
Hangzhou 8
Johannesburg 8
Totale 7.653
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Nome #
On the thermo-mechanical behaviour of DEMO water-cooled lithium lead equatorial outboard blanket module 351
Analysis of a Station Black-Out transient in SMR by using the TRACE and RELAP5 code 309
Analysis of the thermo-mechanical behaviour of the DEMO Water-Cooled Lithium Lead breeding blanket module under normal operation steady state conditions 276
On the influence of the supporting frame on the nuclear response of the Helium-Cooled Lithium Lead Test Blanket Module for ITER 238
A study of the potential influence of frame coolant on HCLL-TBM nuclear response 237
Studies on the AGN - 201 "COSTANZA" Research Reactor 230
A neutron point kinetic model for fusion relevant calculations 228
A study of the potential influence of frame coolant distribution on the radiation-induced damage of HCLL-TBM structural material 225
On the nuclear response of the helium-cooled lithium lead test blanket module in ITER 223
On the nuclear response of the water-cooled Pb-17Li test blanket module for ITER-FEAT 220
On the numerical assessment of the thermo-mechanical performances of the DEMO Helium-Cooled Pebble Bed breeding blanket module 218
On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material 215
Neutronic and photonic analysis of the water-cooled Pb-17Li test blanket module for ITER-FEAT 213
A multi-physics integrated approach to breeding blanket modelling and design 211
A Training Experience of Operators with the AGN-201 “Costanza” Research Reactor of Palermo University 209
Thermal-mechanical and thermal-hydraulic integrated study of the Helium-Cooled Lithium Lead Test Blanket Module 207
First Flight Escape Probability and Uncollided Flux of Nuclear Particles in Convex Bodies with Spherical Symmetry 202
Nuclear Analysis of an ITER Blanket Module 200
Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System 195
On the optimization of the first wall of the DEMO water-cooled lithium lead outboard breeding blanket equatorial module 194
Probabilità di fuga di "particelle" nucleari da corpi a simmetria sferica 193
Assessment of the Possible Lay-Out Influence on the HCLL-TBM Nuclear Response 190
Multi-Module vs. Single-Module concept: Comparison of thermomechanical performances for the DEMO Water-Cooled Lithium Lead breeding blanket 190
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 184
On the AGN - 201 "COSTANZA" Research Reactor at the Department of Nuclear Engineering of the University of Palermo 183
Analysis of the thermo-mechanical behaviour of the DEMO Water-Cooled Lithium Lead breeding blanket module under normal operation steady state conditions 182
Validation of Multi-Physics Integrated Procedure for the HCPB Breeding Blanket 176
Education and Research in Nuclear Engineering and Radiological Protection at Nuclear Engineering Department of Palermo University 174
Study of the helium-cooled lithium lead test blanket module nuclear behaviour under irradiation in ITER 172
On the adoption of the Monte Carlo method to solve one-dimensional steady state thermal diffusion problems for non-uniform solids 170
Numerical assessment of the thermomechanical behaviour of the DEMO Water-Cooled Lithium Lead inboard blanket equatorial module 170
On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material 169
Optimization of the breeder zone cooling tubes of the DEMO Water-Cooled Lithium Lead breeding blanket 167
Investigation of the DEMO WCLL Breeding Blanket Cooling Water Activation 163
Analisi Mediante Il Codice TRACE Delle Principali Fenomenologie Caratterizzanti Il Transitorio Conseguente Ad Una Rottura A Ghigliottina Nella Linea DVI dell’Impianto Sperimentale SPES-3 161
Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project 161
Assessment of the Thermo-mechanical Performances of a DEMO Water-Cooled Liquid Metal Blanket Module 160
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 158
Assessment of the importance of neutron multiplication for tritium production 158
Adeguamento dello SPES2 per Prove di Sicurezza. Analisi Preliminari per La Simulazione di un Incidente Tipo Fukushima su SPES-2 156
Hypothetical porous medium concept as a virtual swirl tape: A novel modelling technique towards efficient CFD simulation of swirl tape cooling pipe 154
Production and transport modelling of Po-210 in DEMO reactor 154
Analysis of a Generation 3+ Pressurised Water Reactor plant response to a postulated Station Black Out 152
Preliminary thermo-mechanical assessment of the Top Cap region of the Water-Cooled Lead-Ceramic Breeder Breeding Blanket alternative concept 149
Analysis of the SPES-3 direct vessel injection line break by using TRACE code 146
Validazione e Verifica (V&V) di CATHARE2 e TRACE sul Programma Sperimentale SPES-2 146
Applicazione del metodo Monte Carlo a problemi monodimensionali di conduzione termica stazionaria in sistemi con conducibilità dipendente dalla posizione 145
Structural analysis of the back supporting structure of the DEMO WCLL outboard blanket 144
On the improved current pulse method for the dynamic assessment of thermal diffusive properties 143
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 142
Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems 141
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 141
Structural assessment of the EU-DEMO WCLL Central Outboard Blanket segment under normal and off-normal operating conditions 140
A Monte Carlo study on the possible lay-out influence in the HCLL-TBM nuclear response 138
TRACE input model for SPES3 facility 135
Modifiche del Codice RELAP5 per lo Studio delle Perdite di Carico in Generatori di Vapore a Tubi Elicoidali Interessati da Flussi Bifase 134
ANALYSES OF THE SPES-3 DESIGN AND BEYOND DESIGN ACCIDENT CONDITION BY USING TRACE CODE 132
Una variante del problema dell'ago di Buffon e verifica con il metodo Monte Carlo 131
Fattibilità di una diversa configurazione della facility SPES-3 130
Assessment of DEMO WCLL breeding blanket primary heat transfer system isolation valve absorbed doses due to activated water 129
Parametric study of the influence of First Wall cooling water on the Water Cooled Lithium Lead Breeding Blanket nuclear response 123
Multiphysics Optimization for First Wall Design Enhancement in Water-Cooled Breeding Blankets 115
On the modelling of tritium transport phenomena at fluid-structure interfaces 114
Sul numero delle disposizioni delle N parti dell'intero M nel caso in cui nessuna delle parti possa essere superiore a Q 112
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 111
Thermal-hydraulic study of the Primary Heat Transport System of the DEMO Divertor Cassette Body 108
Development and application of an alternative modelling approach for the thermo-mechanical analysis of a DEMO water-cooled lithium lead breeding blanket segment 107
Numerical investigation of the structural performances of the EU-DEMO Water-Cooled Lead Lithium breeding blanket equipped with helicoidal double-walled tubes 106
Implementazione ed utilizzo di simulatori semplificati “Desktop” 106
Thermofluid-dynamic and thermal–structural assessment of the EU-DEMO WCLL “double bundle” Breeding Blanket concept left outboard segment 104
Activated corrosion product contamination assessments of DEMO WCLL breeding blanket primary heat transport system 102
Water activation products generation and transport in DEMO divertor 101
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 95
Embrittlement of WCLL blanket and its fracture mechanical assessment 93
Thermal–hydraulic study of the Primary Heat Transport System of the EU-DEMO Divertor Plasma Facing Components 89
Thermal and structural analysis of the European water-cooled lithium lead breeding blanket concept in the L-H mode transition 82
Thermofluid-dynamic assessment of the dual cooling scheme EU-DEMO divertor cassette 74
Feasibility of D-D start-up under realistic technological assumptions for EU-DEMO 72
null 70
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 66
Coolant contamination in gas-cooled reactors due to neutronic sputtering 49
Totale 12.863
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Categoria #
all - tutte 44.089
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 44.089
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2021/2022560 0 0 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
2025/20264.499 299 145 306 244 423 686 661 561 328 489 147 210
2026/20271.104 222 171 711 0 0 0 0 0 0 0 0 0
Totale 12.863