ENEA-IRIS Open Archive è l’archivio della produzione scientifica dell'ENEA, realizzato con l'obiettivo di raccogliere, catalogare e rendere facilmente accessibili in rete i risultati della ricerca. Gli autori dell’ENEA provvedono a depositare le proprie pubblicazioni (articoli su rivista, presentazioni a congressi, report, ecc.). In particolare, quelle finanziate dalla Commissione Europea nell’ambito del programma H2020 (che prevede il deposito obbligatorio in un Repository), una volta caricate, vengono automaticamente importate dal portale europeo OpenAIRE. È possibile inserire, o importare direttamente dalle banche dati previste, le informazioni descrittive del documento e anche allegare, ove consentito dalla normativa sul diritto d'autore, il testo completo della pubblicazione.

ENEA-IRIS Open Archive utilizza la piattaforma IRIS (Institutional Research Information System) sviluppata da CINECA.

DEL NEVO, ALESSANDRO
 Distribuzione geografica
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Continente #
EU - Europa 8.073
NA - Nord America 4.371
AS - Asia 2.003
SA - Sud America 616
AF - Africa 37
Continente sconosciuto - Info sul continente non disponibili 17
OC - Oceania 10
Totale 15.127
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Nazione #
RU - Federazione Russa 4.033
US - Stati Uniti d'America 4.033
IT - Italia 1.104
DE - Germania 990
CN - Cina 758
BR - Brasile 557
SG - Singapore 547
GB - Regno Unito 529
SE - Svezia 439
FI - Finlandia 400
CA - Canada 306
HK - Hong Kong 290
FR - Francia 191
JP - Giappone 153
NL - Olanda 77
BE - Belgio 69
AT - Austria 68
VN - Vietnam 60
IN - India 54
CH - Svizzera 23
GR - Grecia 23
AR - Argentina 21
PL - Polonia 20
UA - Ucraina 19
RO - Romania 17
ES - Italia 16
EU - Europa 15
MX - Messico 13
PK - Pakistan 13
CO - Colombia 12
TR - Turchia 12
UZ - Uzbekistan 12
ZA - Sudafrica 12
CZ - Repubblica Ceca 11
HU - Ungheria 11
MA - Marocco 11
IQ - Iraq 10
KR - Corea 10
BD - Bangladesh 9
JO - Giordania 9
KZ - Kazakistan 9
AU - Australia 7
AZ - Azerbaigian 7
EC - Ecuador 7
JM - Giamaica 7
VE - Venezuela 7
IL - Israele 6
IR - Iran 6
LT - Lituania 6
TH - Thailandia 6
TN - Tunisia 6
AL - Albania 5
IE - Irlanda 5
OM - Oman 5
PT - Portogallo 5
CL - Cile 4
PA - Panama 4
SK - Slovacchia (Repubblica Slovacca) 4
TW - Taiwan 4
AE - Emirati Arabi Uniti 3
GE - Georgia 3
NP - Nepal 3
PY - Paraguay 3
SA - Arabia Saudita 3
AM - Armenia 2
BO - Bolivia 2
CR - Costa Rica 2
DO - Repubblica Dominicana 2
DZ - Algeria 2
EG - Egitto 2
IS - Islanda 2
KW - Kuwait 2
LB - Libano 2
LV - Lettonia 2
NZ - Nuova Zelanda 2
PE - Perù 2
XK - ???statistics.table.value.countryCode.XK??? 2
AO - Angola 1
BB - Barbados 1
BH - Bahrain 1
BS - Bahamas 1
DK - Danimarca 1
GA - Gabon 1
HN - Honduras 1
KE - Kenya 1
LA - Repubblica Popolare Democratica del Laos 1
LU - Lussemburgo 1
MD - Moldavia 1
ML - Mali 1
NI - Nicaragua 1
PF - Polinesia Francese 1
PH - Filippine 1
PS - Palestinian Territory 1
QA - Qatar 1
SI - Slovenia 1
UY - Uruguay 1
Totale 15.127
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Città #
Moscow 1.232
Chandler 1.180
Munich 411
Santa Clara 375
Boardman 294
San Mateo 285
Toronto 284
Ashburn 273
Southend 267
Hamburg 261
Helsinki 245
Hong Kong 241
Singapore 169
New York 144
Beijing 141
Rome 122
Berlin 109
Lappeenranta 102
The Dalles 91
Los Angeles 82
Milan 67
Miami 64
Brussels 60
Turin 59
Dong Ket 58
Las Vegas 57
Shanghai 56
Falkenstein 54
Guangzhou 50
Marseille 48
Vienna 47
Redwood City 39
Ann Arbor 38
São Paulo 36
Bologna 35
Council Bluffs 32
Washington 32
Mountain View 30
Nuremberg 29
Turku 29
Frankfurt am Main 26
Trenton 26
Pisa 24
Amsterdam 21
Central 21
Mazzano Romano 17
Tokyo 17
Tortona 17
Wilmington 17
Belo Horizonte 16
Jyväskylä 15
Chicago 14
London 14
Lyon 14
Paris 13
Falls Church 12
Richardson 12
Shenzhen 12
Qingdao 11
Rio de Janeiro 11
Serra 11
Tashkent 11
Cham 10
Düsseldorf 10
San Francisco 10
Stockholm 10
Budapest 9
Fortaleza 9
Lucca 9
Redmond 9
Xian 9
Amman 8
Borås 8
Bucharest 8
Campinas 8
Neive 8
Phoenix 8
Ribeirão Preto 8
San Nicola 8
Santo André 8
St Petersburg 8
Venice 8
Bra 7
Brasília 7
Darien 7
Ferrara 7
Florence 7
Johannesburg 7
Warsaw 7
Zhengzhou 7
Baku 6
Bergamo 6
Brooklyn 6
Chongqing 6
Curitiba 6
Genoa 6
Goiânia 6
Jinan 6
Nanjing 6
Padova 6
Totale 7.869
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Nome #
Coupled simulations of natural and forced circulation tests in Nacie facility using relap5 and Ansys fluent codes 261
Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment 256
ALFRED-SGBT. Preliminary characterization by the HERO test section 254
Assessment of SIMMER-III code in predicting water cooled lithium lead breeding blanket “in-box-Loss of Coolant Accident” 253
Caratterizzazione sperimentale dell'interazione metallo liquido pesante - acqua e qualifica rottura generatore di vapore LFR 241
Overview on lead-cooled fast reactor design and related technologies development in ENEA 238
Experimental campaign in support of the safety studies of the STGR in LFR 222
Pre-test analysis of thermal-hydraulic behaviour of the NACIE facility for the characterization of a fuel pin bundle 210
Characterization of leak detection in HLM system using LIFUS5/MOD3 facility 208
Status of Pb-16Li technologies for European DEMO fusion reactor 206
Raccolta delle relazioni di partecipazione ai comitati e gruppi internazionali sul nucIeare da fissione 195
GEN-IV LFR development: Status & perspectives 180
Fusion technologies development at ENEA Brasimone Research Centre: Status and perspectives 175
Modeling and analysis of nuclear fuel pin behavior for innovative lead cooled FBR 171
Analisi del comportamento del combustibile MOX ad elevato burnup in condizioni di normal operation e DBA 168
Optimization of the first wall cooling system for the DEMO WCLL blanket 168
Development of best estimate numerical tools for LFR design and safety analysis 159
Analisi di pre-test della campagna sperimentale CIRCE/HERO con codici di sistema 158
CIRCE experimental set-up design and test matrix definition 157
Development and validation of an approach and numerical models for safety analysis of FBR 156
Experimental investigation in LIFUS5/Mod2 facility of spiral-tube steam Generator Rupture scenarios for ELFR 141
Development of best estimate numerical tools for LFR design and safety analysis (2018) 141
Advancement in FGR modeling for transient analysis of FR fuel 141
Development of best estimate numerical tools for LFR design and safety analysis 140
DEMO port plug design and integration studies 139
Post-test of the sgtr experimental tests carried out in the LIFUS facility 137
Benchmark and preliminary validation of the thermal-hydraulic module of the FRENETIC code against EBR-II data 137
Activities in Support to the Assessment of Steam Generator Bayonet Tubes, for GEN-IV Applications 136
Thermal-hydraulic modeling and analyses of the water-cooled EU DEMO using RELAP5 system code 134
Divertor Tokamak Test facility project: status of design and implementation 132
Progettazione e implementazione di un sistema per la rilevazione di piccole perdite. Design and follow-up of a LBE/water leakage detection system 132
Experimental and numerical investigations of interaction between heavy liquid metal and water for supporting the safety of LFR GEN. IV reator design 131
Investigation on cooling performance of WCLL breeding blanket first wall for EU DEMO 130
MHD issues related to the use of Lithium Lead eutectic as breeder material for blankets of fusion power plants 129
Design and preliminary analyses of the new Water Cooled Lithium Lead TBM for ITER 129
Assessment of DEMO WCLL breeding blanket primary heat transfer system isolation valve absorbed doses due to activated water 128
Test di caratterizzazione sperimentale del sistema per la rilevazione di piccole perdite nel Generatore di Vapore LFR 127
ALFRED-SGBT. Preliminary characterization by the HERO test section 127
Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project 126
Thermal-hydraulic modeling and analysis of the Water Cooling System for the ITER Test Blanket Module 126
Alternative design of DEMO Water Cooled Lithium Lead internal structure 125
RELAP5-3D three-dimensional analysis based on Phénix dissymmetric transient test 125
Test di caratterizzazione sperimentale del sistema per la rilevazione di piccole perdite nel Generatore di Vapore LFR 124
Qualification of TRACE V5.0 code against fast cooldown transient in the pkl-iii integral test facility 123
Test Series D experimental results for SIMMER code validation of WCLL BB in-box LOCA in LIFUS5/Mod3 facility 123
Experimental Characterization of Leak Detection Systems in HLM Pool Using LIFUS5/Mod3 Facility 123
Preliminary system modeling for the EUROfusion water cooled lithium lead blanket 122
Experimental investigation of spiral tubes steam generator rupture scenarios in LIFUS5/MOD2 facility for ELFR 122
Parametric study of the influence of double-walled tubes layout on the DEMO WCLL breeding blanket thermal performances 121
Pre-conceptual design of EU DEMO balance of plant systems: Objectives and challenges 120
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications 120
Parametric thermal-hydraulic analysis of the EU DEMO Water-Cooled Lithium-Lead First Wall using the GETTHEM code 119
Development of a SIMMERRELAP5 coupling tool 119
Steam Generator mock-up preliminary design suitable for Pb-Li technology demonstration and code assessment 119
Design dell’esperimento e specifica tecnica di fornitura relativa all’up-grade dell’impianto LIFUS5/Mod2 118
On the impact of the heat transfer modelling approach on the prediction of EU-DEMO WCLL breeding blanket thermal performances 118
RELAP5/SIMMER-III code coupling development for PbLi-water interaction 117
Development of the neutronic module and benchmark and validation of the thermal-hydraulic module of the FRENETIC code 114
Design of a Prototypical Mock-Up for the Experimental Investigation of WCLL First-Wall Performances 113
Development of a model for the thermal-hydraulic characterization of the He-FUS3 loop 113
Investigation of heat transfer in a steam generator bayonet tube for the development of PbLi technology for EU DEMO fusion reactor 112
Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System 111
Assessment of SIMMER-III code based on steam generator tube rupture experiments in LIFUS5/Mod2 facility 111
Simulation study of pressure trends in the case of loss of coolant accident in Water Cooled Lithium Lead blanket module 110
Sviluppo e validazione di un approccio e di modelli per le analisi di sicurezza di reattori veloci di IV generazione 109
EBR-II passive safety demonstration tests benchmark analyses-phase 2 109
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 109
Nuclear analysis of the Water cooled lithium lead DEMO reactor 108
Hero test section for experimental investigation of steam generator bayonet tube of ALFRED 107
Parametric study of the influence of First Wall cooling water on the Water Cooled Lithium Lead Breeding Blanket nuclear response 106
Thermal-hydraulic analysis of the DEMO WCLL elementary cell: BZ tubes layout optimization 106
Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems 106
Preliminary design of the top cap of DEMO Water-Cooled Lithium Lead breeding blanket segments 105
MHD pressure drop estimate for the WCLL in-magnet PbLi loop 105
Investigation of the DEMO WCLL Breeding Blanket Cooling Water Activation 105
Updated design of water-cooled breeder blanket for CFETR 105
Nuclear performances of the water-cooled lithium lead DEMO reactor: Neutronic analysis on a fully heterogeneous model 104
On the effect of stiffening plates configuration on the DEMO Water Cooled Lithium Lead Breeding Blanket module thermo-mechanical behaviour 104
Thermal-hydraulic and thermo-mechanical simulations of Water-Heavy Liquid Metal interactions towards the DEMO WCLL breeding blanket design 104
MHD mixed convection flow in the WCLL: Heat transfer analysis and cooling system optimization 104
Influence of PbLi hydraulic path and integration layout on MHD pressure losses 104
System thermal-hydraulic modelling of the phénix dissymmetric test benchmark 103
Thermo-hydraulic analysis of EU DEMO WCLL breeding blanket 102
Post-test analysis of SHRT45R transient performed on the EBR-II FR 102
Parametric thermal analysis for the optimization of Double Walled Tubes layout in the Water Cooled Lithium Lead inboard blanket of DEMO fusion reactor 102
Preliminary analysis of an in-box LOCA in the breeding unit of the WCLL TBM for the ITER reactor with SIMMER-IV code 101
Installazione della sezione di prova Hero nella facility Circe: sviluppo nodalizzazione e progettazione della campagna sperimentale 99
Validazione e analisi dei gas di fissione in combustibili MOX ad elevato burnup 99
Fornitura scambiatore di calore a tubi a baionetta 99
Preliminary design of a helical coil steam generator mock-up for the CIRCE facility for the development of DEMO LiPb heat exchanger 98
IAEA's coordinated research project on EBR-II Shutdown heat removal tests 98
Qualification of a RELAP5-3D © system code nodalization of EBR-II 98
Systems engineering activities supporting the heating & current drive and fuelling lines systems integration in the European DEMO breeding blanket 98
Maturation of critical technologies for the DEMO balance of plant systems 97
Analysis of the thermal-hydraulic behavior of the EU-DEMO WCLL breeding blanket cooling systems during a loss of flow accident 97
Development of a PbLi heat exchanger for EU DEMO fusion reactor: Experimental test and system code assessment 96
Experimental analysis of stationary and transient scenarios of alfred steam generator bayonet tube in circe-hero facility 96
The demo water-cooled lead–lithium breeding blanket: Design status at the end of the pre-conceptual design phase 96
Experimental investigation and SIMMER-III code modelling of LBE-water interaction in LIFUS5/Mod2 facility 95
Deterministic safety analysis of Station Blackout postulated accident on the basis of the SMR simulator MASLWR 95
Totale 13.212
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Categoria #
all - tutte 78.893
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 78.893
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/202023 0 0 0 0 0 0 0 0 0 0 0 23
2020/20211.057 13 19 10 19 172 10 24 99 86 123 346 136
2021/20221.323 39 320 55 75 154 33 63 271 82 25 71 135
2022/20232.576 191 478 182 372 98 433 44 227 330 83 69 69
2023/20241.822 109 69 201 44 145 350 97 155 114 148 128 262
2024/20258.431 75 396 114 169 543 446 661 601 692 341 2.948 1.445
Totale 15.370