Archivio istituzionale della ricerca dell'Università degli Studi di Palermo

CHIOVARO, Pierluigi
 Distribuzione geografica
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Continente #
NA - Nord America 3.951
EU - Europa 1.607
AS - Asia 592
SA - Sud America 29
AF - Africa 18
Continente sconosciuto - Info sul continente non disponibili 1
OC - Oceania 1
Totale 6.199
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Nazione #
US - Stati Uniti d'America 3.947
IT - Italia 609
CN - Cina 281
FI - Finlandia 271
SG - Singapore 261
UA - Ucraina 196
DE - Germania 137
IE - Irlanda 114
GB - Regno Unito 70
SE - Svezia 41
RU - Federazione Russa 38
BR - Brasile 25
FR - Francia 19
NL - Olanda 17
CH - Svizzera 15
KR - Corea 13
CI - Costa d'Avorio 12
RO - Romania 12
BE - Belgio 11
GR - Grecia 11
IN - India 10
PL - Polonia 9
AT - Austria 8
MT - Malta 7
ES - Italia 6
HK - Hong Kong 6
JP - Giappone 6
SI - Slovenia 5
CZ - Repubblica Ceca 4
DZ - Algeria 4
UZ - Uzbekistan 4
CA - Canada 2
IR - Iran 2
MX - Messico 2
MY - Malesia 2
PE - Perù 2
A2 - ???statistics.table.value.countryCode.A2??? 1
AU - Australia 1
BD - Bangladesh 1
CO - Colombia 1
DK - Danimarca 1
EE - Estonia 1
HR - Croazia 1
IL - Israele 1
JO - Giordania 1
KG - Kirghizistan 1
LB - Libano 1
MD - Moldavia 1
NO - Norvegia 1
OM - Oman 1
PT - Portogallo 1
PY - Paraguay 1
SD - Sudan 1
SK - Slovacchia (Repubblica Slovacca) 1
TR - Turchia 1
ZA - Sudafrica 1
Totale 6.199
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Città #
Fairfield 556
Chandler 409
Ashburn 359
Woodbridge 287
Houston 284
Wilmington 239
Seattle 227
Cambridge 210
Singapore 209
Ann Arbor 189
Palermo 155
Des Moines 111
Dublin 111
Medford 92
Jacksonville 84
Princeton 64
Helsinki 58
Altamura 57
Nanjing 55
Munich 49
Rome 40
Dearborn 39
Lawrence 35
San Diego 35
Santa Clara 32
Boardman 31
Beijing 27
Tulsa 26
Changsha 25
Milan 25
New York 25
Shenyang 22
Venice 19
Jinan 17
Ludwigshafen am Rhein 17
Nanchang 17
London 15
Guangzhou 13
Jiaxing 13
Seongnam 13
Abidjan 12
Saint Petersburg 12
Amsterdam 11
Brussels 11
Norwalk 11
Zurich 11
Ningbo 10
Hebei 9
Pune 9
Falkenstein 8
Redmond 8
San Paolo di Civitate 8
Tianjin 8
Zhengzhou 8
Attard 7
Columbus 7
Hefei 7
Lappeenranta 7
Verona 7
Warsaw 7
Auburn Hills 6
Bologna 6
Carini 6
Council Bluffs 6
Washington 6
Chicago 5
Haikou 5
Kunming 5
Ljubljana 5
Los Angeles 5
Redwood City 5
Turin 5
Vienna 5
Falls Church 4
Hong Kong 4
Kilburn 4
Lanzhou 4
Mountain View 4
Upland 4
West Jordan 4
Bagheria 3
Bilbao 3
Frankfurt Am Main 3
Hangzhou 3
Indiana 3
Nuremberg 3
Orange 3
Santarcangelo 3
Serra 3
Shanghai 3
Tashkent 3
Termini Imerese 3
Tokyo 3
Torino 3
Agrigento 2
Alessandria 2
Anzio 2
Cassino 2
Catania 2
Central 2
Totale 4.621
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Nome #
On the thermo-mechanical behaviour of DEMO water-cooled lithium lead equatorial outboard blanket module 307
Analysis of the thermo-mechanical behaviour of the DEMO Water-Cooled Lithium Lead breeding blanket module under normal operation steady state conditions 181
Analysis of a Station Black-Out transient in SMR by using the TRACE and RELAP5 code 175
On the nuclear response of the helium-cooled lithium lead test blanket module in ITER 154
On the influence of the supporting frame on the nuclear response of the Helium-Cooled Lithium Lead Test Blanket Module for ITER 148
On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material 148
A neutron point kinetic model for fusion relevant calculations 148
On the nuclear response of the water-cooled Pb-17Li test blanket module for ITER-FEAT 147
Thermal-mechanical and thermal-hydraulic integrated study of the Helium-Cooled Lithium Lead Test Blanket Module 145
A study of the potential influence of frame coolant on HCLL-TBM nuclear response 142
On the numerical assessment of the thermo-mechanical performances of the DEMO Helium-Cooled Pebble Bed breeding blanket module 141
Neutronic and photonic analysis of the water-cooled Pb-17Li test blanket module for ITER-FEAT 140
A study of the potential influence of frame coolant distribution on the radiation-induced damage of HCLL-TBM structural material 139
Assessment of the Possible Lay-Out Influence on the HCLL-TBM Nuclear Response 136
First Flight Escape Probability and Uncollided Flux of Nuclear Particles in Convex Bodies with Spherical Symmetry 130
Probabilità di fuga di "particelle" nucleari da corpi a simmetria sferica 128
On the optimization of the first wall of the DEMO water-cooled lithium lead outboard breeding blanket equatorial module 126
Study of the helium-cooled lithium lead test blanket module nuclear behaviour under irradiation in ITER 125
Nuclear Analysis of an ITER Blanket Module 125
Studies on the AGN - 201 "COSTANZA" Research Reactor 120
Optimization of the breeder zone cooling tubes of the DEMO Water-Cooled Lithium Lead breeding blanket 115
A multi-physics integrated approach to breeding blanket modelling and design 112
On the adoption of the Monte Carlo method to solve one-dimensional steady state thermal diffusion problems for non-uniform solids 111
Multi-Module vs. Single-Module concept: Comparison of thermomechanical performances for the DEMO Water-Cooled Lithium Lead breeding blanket 109
Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System 107
Structural analysis of the back supporting structure of the DEMO WCLL outboard blanket 104
Numerical assessment of the thermomechanical behaviour of the DEMO Water-Cooled Lithium Lead inboard blanket equatorial module 101
Validation of Multi-Physics Integrated Procedure for the HCPB Breeding Blanket 101
On the AGN - 201 "COSTANZA" Research Reactor at the Department of Nuclear Engineering of the University of Palermo 98
A Training Experience of Operators with the AGN-201 “Costanza” Research Reactor of Palermo University 98
On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material 96
Assessment of the importance of neutron multiplication for tritium production 95
Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project 90
Investigation of the DEMO WCLL Breeding Blanket Cooling Water Activation 85
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 84
Analysis of the thermo-mechanical behaviour of the DEMO Water-Cooled Lithium Lead breeding blanket module under normal operation steady state conditions 82
Education and Research in Nuclear Engineering and Radiological Protection at Nuclear Engineering Department of Palermo University 81
On the improved current pulse method for the dynamic assessment of thermal diffusive properties 79
Parametric study of the influence of First Wall cooling water on the Water Cooled Lithium Lead Breeding Blanket nuclear response 77
Applicazione del metodo Monte Carlo a problemi monodimensionali di conduzione termica stazionaria in sistemi con conducibilità dipendente dalla posizione 76
Assessment of the Thermo-mechanical Performances of a DEMO Water-Cooled Liquid Metal Blanket Module 76
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 73
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 71
Validazione e Verifica (V&V) di CATHARE2 e TRACE sul Programma Sperimentale SPES-2 71
null 70
Structural assessment of the EU-DEMO WCLL Central Outboard Blanket segment under normal and off-normal operating conditions 69
TRACE input model for SPES3 facility 68
A Monte Carlo study on the possible lay-out influence in the HCLL-TBM nuclear response 67
Adeguamento dello SPES2 per Prove di Sicurezza. Analisi Preliminari per La Simulazione di un Incidente Tipo Fukushima su SPES-2 66
Analysis of the SPES-3 direct vessel injection line break by using TRACE code 65
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 65
ANALYSES OF THE SPES-3 DESIGN AND BEYOND DESIGN ACCIDENT CONDITION BY USING TRACE CODE 61
Modifiche del Codice RELAP5 per lo Studio delle Perdite di Carico in Generatori di Vapore a Tubi Elicoidali Interessati da Flussi Bifase 60
Una variante del problema dell'ago di Buffon e verifica con il metodo Monte Carlo 58
Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems 58
Fattibilità di una diversa configurazione della facility SPES-3 53
Sul numero delle disposizioni delle N parti dell'intero M nel caso in cui nessuna delle parti possa essere superiore a Q 51
Production and transport modelling of Po-210 in DEMO reactor 48
Analysis of a Generation 3+ Pressurised Water Reactor plant response to a postulated Station Black Out 48
Hypothetical porous medium concept as a virtual swirl tape: A novel modelling technique towards efficient CFD simulation of swirl tape cooling pipe 46
On the modelling of tritium transport phenomena at fluid-structure interfaces 46
Implementazione ed utilizzo di simulatori semplificati “Desktop” 45
Multiphysics Optimization for First Wall Design Enhancement in Water-Cooled Breeding Blankets 45
Assessment of DEMO WCLL breeding blanket primary heat transfer system isolation valve absorbed doses due to activated water 44
Thermal-hydraulic study of the Primary Heat Transport System of the DEMO Divertor Cassette Body 33
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 27
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 26
Development and application of an alternative modelling approach for the thermo-mechanical analysis of a DEMO water-cooled lithium lead breeding blanket segment 23
Preliminary thermo-mechanical assessment of the Top Cap region of the Water-Cooled Lead-Ceramic Breeder Breeding Blanket alternative concept 17
Thermal and structural analysis of the European water-cooled lithium lead breeding blanket concept in the L-H mode transition 12
Activated corrosion product contamination assessments of DEMO WCLL breeding blanket primary heat transport system 12
Thermofluid-dynamic and thermal–structural assessment of the EU-DEMO WCLL “double bundle” Breeding Blanket concept left outboard segment 12
Numerical investigation of the structural performances of the EU-DEMO Water-Cooled Lead Lithium breeding blanket equipped with helicoidal double-walled tubes 11
Feasibility of D-D start-up under realistic technological assumptions for EU-DEMO 11
Thermal–hydraulic study of the Primary Heat Transport System of the EU-DEMO Divertor Plasma Facing Components 9
Water activation products generation and transport in DEMO divertor 7
Embrittlement of WCLL blanket and its fracture mechanical assessment 7
Totale 6.537
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Categoria #
all - tutte 26.456
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 26.456
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/2020496 0 0 0 0 0 0 0 107 191 83 70 45
2020/2021867 31 157 130 65 64 27 41 67 87 70 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
2024/2025734 13 115 104 91 41 147 159 64 0 0 0 0
Totale 6.537