DEL NEVO, ALESSANDRO
 Distribuzione geografica
Continente #
NA - Nord America 2450
EU - Europa 2113
AS - Asia 352
Continente sconosciuto - Info sul continente non disponibili 15
OC - Oceania 5
AF - Africa 2
Totale 4937
Nazione #
US - Stati Uniti d'America 2163
IT - Italia 615
GB - Regno Unito 500
SE - Svezia 434
CA - Canada 286
DE - Germania 195
CN - Cina 172
AT - Austria 98
BE - Belgio 85
VN - Vietnam 58
FI - Finlandia 56
FR - Francia 49
HK - Hong Kong 44
IN - India 43
GR - Grecia 19
NL - Olanda 17
EU - Europa 15
RO - Romania 15
JP - Giappone 9
HU - Ungheria 7
KR - Corea 7
ES - Italia 6
UA - Ucraina 6
IR - Iran 5
SG - Singapore 5
AU - Australia 4
CH - Svizzera 4
RU - Federazione Russa 3
TH - Thailandia 3
PK - Pakistan 2
TR - Turchia 2
DZ - Algeria 1
LU - Lussemburgo 1
MD - Moldavia 1
MX - Messico 1
PF - Polinesia Francese 1
PL - Polonia 1
PT - Portogallo 1
SA - Arabia Saudita 1
TW - Taiwan 1
ZA - Sudafrica 1
Totale 4937
Città #
Chandler 1180
San Mateo 285
Toronto 275
Southend 267
Berlin 109
Brussels 80
Vienna 74
Rome 72
Dong Ket 58
Helsinki 56
Beijing 39
Redwood City 39
Ann Arbor 38
Guangzhou 35
Shanghai 32
Milan 30
Mountain View 30
Bologna 20
Los Angeles 20
Turin 20
Central 18
Mazzano Romano 17
Wilmington 17
Chicago 14
Falls Church 12
Richardson 12
Las Vegas 11
Hanover 10
Paris 10
Redmond 9
Serra 9
Xian 9
Borås 8
Neive 8
San Nicola 8
Bra 7
Bucharest 7
Budapest 7
Darien 7
Tortona 7
Ferrara 6
Genoa 6
London 6
Pisa 6
Shenzhen 6
Zhengzhou 6
Central District 5
Chongqing 5
Karlsruhe 5
Leopoldshafen 5
Nanjing 5
Palermo 5
Rockville 5
Stockholm 5
Stuttgart 5
Varese 5
Woodbridge 5
Como 4
Florence 4
Mississauga 4
Noicattaro 4
Padova 4
Raleigh 4
Tokyo 4
Aprilia 3
Bang Klam 3
Bangalore 3
Fossano 3
Garching 3
Genova 3
Heusden-Zolder 3
Madrid 3
Montecatini Terme 3
Montegaldella 3
Mumbai 3
Pescia 3
Quiliano 3
San Salvatore Telesino 3
Santa Giustina in Colle 3
Treviso 3
Verzuolo 3
Wuhan 3
Yonkers 3
Alba Adriatica 2
Altopascio 2
Ambivere 2
Bolzano 2
Boydton 2
Bregnano 2
Brooklyn 2
Buffalo 2
Castellabate 2
Chengdu 2
Chennai 2
Didcot 2
Huizen 2
IJsselstein 2
Islamabad 2
Jalandhar 2
Lafayette 2
Totale 3176
Nome #
Characterization of leak detection in HLM system using LIFUS5/MOD3 facility 123
Raccolta delle relazioni di partecipazione ai comitati e gruppi internazionali sul nucIeare da fissione 97
CIRCE experimental set-up design and test matrix definition 94
Experimental campaign in support of the safety studies of the STGR in LFR 93
Pre-test analysis of thermal-hydraulic behaviour of the NACIE facility for the characterization of a fuel pin bundle 91
GEN-IV LFR development: Status & perspectives 84
Development and validation of an approach and numerical models for safety analysis of FBR 84
Modeling and analysis of nuclear fuel pin behavior for innovative lead cooled FBR 84
Development of best estimate numerical tools for LFR design and safety analysis 82
Development of best estimate numerical tools for LFR design and safety analysis (2018) 82
RELAP5-3D three-dimensional analysis based on Phénix dissymmetric transient test 73
Advancement in FGR modeling for transient analysis of FR fuel 71
Fusion technologies development at ENEA Brasimone Research Centre: Status and perspectives 71
Analisi del comportamento del combustibile MOX ad elevato burnup in condizioni di normal operation e DBA 69
Progettazione e implementazione di un sistema per la rilevazione di piccole perdite. Design and follow-up of a LBE/water leakage detection system 68
Development of best estimate numerical tools for LFR design and safety analysis 66
Design and preliminary analyses of the new Water Cooled Lithium Lead TBM for ITER 64
Qualification of TRACE V5.0 code against fast cooldown transient in the pkl-iii integral test facility 62
Experimental and numerical investigations of interaction between heavy liquid metal and water for supporting the safety of LFR GEN. IV reator design 60
Test di caratterizzazione sperimentale del sistema per la rilevazione di piccole perdite nel Generatore di Vapore LFR 57
Test Series D experimental results for SIMMER code validation of WCLL BB in-box LOCA in LIFUS5/Mod3 facility 57
Analisi di pre-test della campagna sperimentale CIRCE/HERO con codici di sistema 56
Thermal-hydraulic modeling and analyses of the water-cooled EU DEMO using RELAP5 system code 55
Overview on lead-cooled fast reactor design and related technologies development in ENEA 54
DEMO port plug design and integration studies 53
Test di caratterizzazione sperimentale del sistema per la rilevazione di piccole perdite nel Generatore di Vapore LFR 53
Activities in Support to the Assessment of Steam Generator Bayonet Tubes, for GEN-IV Applications 52
Design dell’esperimento e specifica tecnica di fornitura relativa all’up-grade dell’impianto LIFUS5/Mod2 52
MHD issues related to the use of Lithium Lead eutectic as breeder material for blankets of fusion power plants 51
Optimization of the first wall cooling system for the DEMO WCLL blanket 51
Assessment of DEMO WCLL breeding blanket primary heat transfer system isolation valve absorbed doses due to activated water 51
Experimental Characterization of Leak Detection Systems in HLM Pool Using LIFUS5/Mod3 Facility 51
Preliminary system modeling for the EUROfusion water cooled lithium lead blanket 50
Experimental investigation in LIFUS5/Mod2 facility of spiral-tube steam Generator Rupture scenarios for ELFR 50
Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project 49
ALFRED-SGBT. Preliminary characterization by the HERO test section 48
Sviluppo e validazione di un approccio e di modelli per le analisi di sicurezza di reattori veloci di IV generazione 48
Hero test section for experimental investigation of steam generator bayonet tube of ALFRED 48
Updated design of water-cooled breeder blanket for CFETR 48
Development of a model for the thermal-hydraulic characterization of the He-FUS3 loop 47
Parametric study of the influence of First Wall cooling water on the Water Cooled Lithium Lead Breeding Blanket nuclear response 47
Steam Generator mock-up preliminary design suitable for Pb-Li technology demonstration and code assessment 47
Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems 47
System thermal-hydraulic modelling of the phénix dissymmetric test benchmark 46
Assessment of SIMMER-III code based on steam generator tube rupture experiments in LIFUS5/Mod2 facility 46
Preliminary design of the top cap of DEMO Water-Cooled Lithium Lead breeding blanket segments 46
Parametric thermal-hydraulic analysis of the EU DEMO Water-Cooled Lithium-Lead First Wall using the GETTHEM code 45
Deterministic safety analysis of Station Blackout postulated accident on the basis of the SMR simulator MASLWR 45
Fornitura scambiatore di calore a tubi a baionetta 45
Alternative design of DEMO Water Cooled Lithium Lead internal structure 45
Parametric study of the influence of double-walled tubes layout on the DEMO WCLL breeding blanket thermal performances 45
Post-test of the sgtr experimental tests carried out in the LIFUS facility 44
Benchmark and preliminary validation of the thermal-hydraulic module of the FRENETIC code against EBR-II data 44
Validation of the 1D+2D thermal-hydraulic module of the FRENETIC code 44
ALFRED-SGBT. Preliminary characterization by the HERO test section 44
Development of a SIMMERRELAP5 coupling tool 44
Coupled simulations of natural and forced circulation tests in Nacie facility using relap5 and Ansys fluent codes 44
Thermal-hydraulic modeling and analysis of the Water Cooling System for the ITER Test Blanket Module 44
Influence of PbLi hydraulic path and integration layout on MHD pressure losses 44
Post-test analysis of SHRT45R transient performed on the EBR-II FR 43
On the impact of the heat transfer modelling approach on the prediction of EU-DEMO WCLL breeding blanket thermal performances 43
Qualification of a RELAP5-3D © system code nodalization of EBR-II 41
Status of Pb-16Li technologies for European DEMO fusion reactor 41
RELAP5/SIMMER-III code coupling development for PbLi-water interaction 41
Experimental investigation and SIMMER-III code modelling of LBE-water interaction in LIFUS5/Mod2 facility 40
Qualifica di codici di calcolo dedicati alle analisi di sistema avanzati quando applicati nella simulazione di impianti a metallo liquido 40
MHD mixed convection flow in the WCLL: Heat transfer analysis and cooling system optimization 40
Supporto alla progettazione del combustibile nucleare per il reattore LFR 39
On the effect of stiffening plates configuration on the DEMO Water Cooled Lithium Lead Breeding Blanket module thermo-mechanical behaviour 39
Thermal-hydraulic and thermo-mechanical simulations of Water-Heavy Liquid Metal interactions towards the DEMO WCLL breeding blanket design 39
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications 39
Thermo-hydraulic analysis of EU DEMO WCLL breeding blanket 38
IAEA's coordinated research project on EBR-II Shutdown heat removal tests 38
Pre-conceptual design of EU DEMO balance of plant systems: Objectives and challenges 37
Nuclear analysis of the Water cooled lithium lead DEMO reactor 37
Investigation of the DEMO WCLL Breeding Blanket Cooling Water Activation 37
Systems engineering activities supporting the heating & current drive and fuelling lines systems integration in the European DEMO breeding blanket 36
Parametric thermal analysis for the optimization of Double Walled Tubes layout in the Water Cooled Lithium Lead inboard blanket of DEMO fusion reactor 36
EBR-II passive safety demonstration tests benchmark analyses-phase 2 35
Thermo-hydraulic analysis of PbLi ancillary system of WCLL TBM undergoing in-box LOCA 35
Installazione della sezione di prova Hero nella facility Circe: sviluppo nodalizzazione e progettazione della campagna sperimentale 34
Post-test simulation of a PLOFA transient test in the CIRCE-HERO facility 33
Investigation on cooling performance of WCLL breeding blanket first wall for EU DEMO 33
Preliminary Thermo-Mechanical Design of the Once through Steam Generator and Molten Salt Intermediate Heat Exchanger for EU DEMO 33
Caratterizzazione sperimentale dell'interazione metallo liquido pesante - acqua e qualifica rottura generatore di vapore LFR 32
Validazione e analisi dei gas di fissione in combustibili MOX ad elevato burnup 31
Experimental investigation of spiral tubes steam generator rupture scenarios in LIFUS5/MOD2 facility for ELFR 31
Investigation of heat transfer in a steam generator bayonet tube for the development of PbLi technology for EU DEMO fusion reactor 31
MHD pressure drop estimate for the WCLL in-magnet PbLi loop 31
Experimental and numerical results of LIFUS5/Mod3 series E test on in-box LOCA transient for WCLL-BB 31
Experimental analysis of stationary and transient scenarios of alfred steam generator bayonet tube in circe-hero facility 30
Thermal-hydraulic analysis of the DEMO WCLL elementary cell: BZ tubes layout optimization 30
Experimental and numerical investigation of double wall bayonet tubes performances in pool type integral test facility 29
Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System 28
MHD forced convection flow in dielectric and electro-conductive rectangular annuli 28
Hybrid 1D + 2D modelling for the assessment of the heat transfer in the EU DEMO water-cooled lithium-lead manifolds 28
Simulation study of pressure trends in the case of loss of coolant accident in Water Cooled Lithium Lead blanket module 27
Thermal-hydraulic code-to-code benchmark in a simplified EBR-II geometry 27
The demo water-cooled lead–lithium breeding blanket: Design status at the end of the pre-conceptual design phase 27
Development of the neutronic module and benchmark and validation of the thermal-hydraulic module of the FRENETIC code 26
Totale 4869
Categoria #
all - tutte 24895
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 24895


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/2020161 0000 817 4715 11231723
2020/20211057 13191019 17210 2499 86123346136
2021/20221323 393205575 15433 63271 822571135
2022/20232596 191478182372 98433 68242 33796918
Totale 5137