statistiche ricercatore

DEL NEVO, ALESSANDRO

Distribuzione geografica

Continente	#
NA - Nord America	3.609
EU - Europa	2.700
AS - Asia	1.002
Continente sconosciuto - Info sul continente non disponibili	15
OC - Oceania	9
SA - Sud America	3
AF - Africa	2
Totale	7.340

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Nazione	#
US - Stati Uniti d'America	3.317
IT - Italia	880
CN - Cina	635
GB - Regno Unito	506
SE - Svezia	434
CA - Canada	291
DE - Germania	209
FI - Finlandia	175
FR - Francia	132
RU - Federazione Russa	131
SG - Singapore	116
HK - Hong Kong	102
BE - Belgio	65
VN - Vietnam	58
AT - Austria	55
IN - India	43
GR - Grecia	22
NL - Olanda	19
JP - Giappone	18
RO - Romania	16
EU - Europa	15
CH - Svizzera	12
ES - Italia	10
HU - Ungheria	9
KR - Corea	9
UA - Ucraina	8
AU - Australia	7
CZ - Repubblica Ceca	6
TH - Thailandia	6
IR - Iran	5
PK - Pakistan	5
PL - Polonia	4
IE - Irlanda	3
TR - Turchia	3
AR - Argentina	1
BR - Brasile	1
CO - Colombia	1
DZ - Algeria	1
LU - Lussemburgo	1
MD - Moldavia	1
MX - Messico	1
NZ - Nuova Zelanda	1
PF - Polinesia Francese	1
PT - Portogallo	1
SA - Arabia Saudita	1
SI - Slovenia	1
TW - Taiwan	1
ZA - Sudafrica	1
Totale	7.340

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Città	#
Chandler	1.180
Boardman	294
San Mateo	285
Toronto	275
Southend	267
Ashburn	258
New York	138
Beijing	122
Berlin	109
Lappeenranta	102
Rome	101
Helsinki	73
Miami	63
Singapore	63
Dong Ket	58
Las Vegas	57
Brussels	56
Hong Kong	55
Milan	53
Los Angeles	52
Marseille	46
Shanghai	45
Guangzhou	44
Turin	42
Vienna	41
Redwood City	39
Ann Arbor	38
Washington	32
Mountain View	30
Bologna	27
Trenton	26
Central	21
Mazzano Romano	17
Tortona	17
Wilmington	17
Chicago	14
Santa Clara	14
Lyon	13
Pisa	13
Falls Church	12
Richardson	12
Paris	11
Shenzhen	11
Qingdao	10
Tokyo	10
Budapest	9
Redmond	9
Serra	9
Xian	9
Borås	8
Neive	8
San Nicola	8
St Petersburg	8
Venice	8
Bra	7
Bucharest	7
Darien	7
London	7
Cham	6
Ferrara	6
Frankfurt am Main	6
Genoa	6
Nanjing	6
Padova	6
Palermo	6
Zhengzhou	6
Bergamo	5
Central District	5
Chongqing	5
Florence	5
Karlsruhe	5
Leopoldshafen	5
Rockville	5
Stockholm	5
Stuttgart	5
Tappahannock	5
Varese	5
Woodbridge	5
Brno	4
Castel Frentano	4
Chengdu	4
Como	4
Fredericton	4
Guiyang	4
Hanover	4
Mississauga	4
Mol	4
Nembro	4
Noicattaro	4
Nuremberg	4
Pavia	4
Pescia	4
Raleigh	4
West Jordan	4
Xi'an	4
Ancona	3
Aprilia	3
Bang Klam	3
Bangalore	3
Bangkok	3
Totale	4.558

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Nome	#
Experimental campaign in support of the safety studies of the STGR in LFR	154
Characterization of leak detection in HLM system using LIFUS5/MOD3 facility	150
Pre-test analysis of thermal-hydraulic behaviour of the NACIE facility for the characterization of a fuel pin bundle	142
Overview on lead-cooled fast reactor design and related technologies development in ENEA	136
Raccolta delle relazioni di partecipazione ai comitati e gruppi internazionali sul nucIeare da fissione	125
GEN-IV LFR development: Status & perspectives	113
Modeling and analysis of nuclear fuel pin behavior for innovative lead cooled FBR	108
Analisi del comportamento del combustibile MOX ad elevato burnup in condizioni di normal operation e DBA	107
CIRCE experimental set-up design and test matrix definition	106
Fusion technologies development at ENEA Brasimone Research Centre: Status and perspectives	102
Development and validation of an approach and numerical models for safety analysis of FBR	101
Development of best estimate numerical tools for LFR design and safety analysis	98
Advancement in FGR modeling for transient analysis of FR fuel	89
Development of best estimate numerical tools for LFR design and safety analysis (2018)	87
RELAP5-3D three-dimensional analysis based on Phénix dissymmetric transient test	87
Development of best estimate numerical tools for LFR design and safety analysis	84
Progettazione e implementazione di un sistema per la rilevazione di piccole perdite. Design and follow-up of a LBE/water leakage detection system	83
Thermal-hydraulic modeling and analyses of the water-cooled EU DEMO using RELAP5 system code	82
Design and preliminary analyses of the new Water Cooled Lithium Lead TBM for ITER	81
Analisi di pre-test della campagna sperimentale CIRCE/HERO con codici di sistema	80
Experimental and numerical investigations of interaction between heavy liquid metal and water for supporting the safety of LFR GEN. IV reator design	79
Test di caratterizzazione sperimentale del sistema per la rilevazione di piccole perdite nel Generatore di Vapore LFR	78
Experimental investigation in LIFUS5/Mod2 facility of spiral-tube steam Generator Rupture scenarios for ELFR	77
Test Series D experimental results for SIMMER code validation of WCLL BB in-box LOCA in LIFUS5/Mod3 facility	77
Qualification of TRACE V5.0 code against fast cooldown transient in the pkl-iii integral test facility	75
MHD issues related to the use of Lithium Lead eutectic as breeder material for blankets of fusion power plants	74
Activities in Support to the Assessment of Steam Generator Bayonet Tubes, for GEN-IV Applications	73
Test di caratterizzazione sperimentale del sistema per la rilevazione di piccole perdite nel Generatore di Vapore LFR	72
DEMO port plug design and integration studies	71
Thermal-hydraulic modeling and analysis of the Water Cooling System for the ITER Test Blanket Module	71
Investigation on cooling performance of WCLL breeding blanket first wall for EU DEMO	70
Assessment of DEMO WCLL breeding blanket primary heat transfer system isolation valve absorbed doses due to activated water	70
Parametric study of the influence of double-walled tubes layout on the DEMO WCLL breeding blanket thermal performances	69
Preliminary system modeling for the EUROfusion water cooled lithium lead blanket	68
Thermal-hydraulic analysis of the DEMO WCLL elementary cell: BZ tubes layout optimization	68
Steam Generator mock-up preliminary design suitable for Pb-Li technology demonstration and code assessment	68
Experimental Characterization of Leak Detection Systems in HLM Pool Using LIFUS5/Mod3 Facility	68
Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project	67
ALFRED-SGBT. Preliminary characterization by the HERO test section	66
ALFRED-SGBT. Preliminary characterization by the HERO test section	66
Assessment of SIMMER-III code based on steam generator tube rupture experiments in LIFUS5/Mod2 facility	66
Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment	65
Design dell’esperimento e specifica tecnica di fornitura relativa all’up-grade dell’impianto LIFUS5/Mod2	65
Hero test section for experimental investigation of steam generator bayonet tube of ALFRED	65
Sviluppo e validazione di un approccio e di modelli per le analisi di sicurezza di reattori veloci di IV generazione	64
Alternative design of DEMO Water Cooled Lithium Lead internal structure	64
On the impact of the heat transfer modelling approach on the prediction of EU-DEMO WCLL breeding blanket thermal performances	64
Optimization of the first wall cooling system for the DEMO WCLL blanket	64
Parametric thermal-hydraulic analysis of the EU DEMO Water-Cooled Lithium-Lead First Wall using the GETTHEM code	63
Development of a model for the thermal-hydraulic characterization of the He-FUS3 loop	63
Coupled simulations of natural and forced circulation tests in Nacie facility using relap5 and Ansys fluent codes	63
Post-test of the sgtr experimental tests carried out in the LIFUS facility	62
Benchmark and preliminary validation of the thermal-hydraulic module of the FRENETIC code against EBR-II data	62
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	62
Development of a SIMMERRELAP5 coupling tool	60
RELAP5/SIMMER-III code coupling development for PbLi-water interaction	60
Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems	60
Thermo-hydraulic analysis of EU DEMO WCLL breeding blanket	59
Fornitura scambiatore di calore a tubi a baionetta	59
Preliminary design of the top cap of DEMO Water-Cooled Lithium Lead breeding blanket segments	59
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications	59
Status of Pb-16Li technologies for European DEMO fusion reactor	58
Experimental investigation of spiral tubes steam generator rupture scenarios in LIFUS5/MOD2 facility for ELFR	58
Nuclear analysis of the Water cooled lithium lead DEMO reactor	58
Deterministic safety analysis of Station Blackout postulated accident on the basis of the SMR simulator MASLWR	57
MHD mixed convection flow in the WCLL: Heat transfer analysis and cooling system optimization	57
Updated design of water-cooled breeder blanket for CFETR	57
Parametric study of the influence of First Wall cooling water on the Water Cooled Lithium Lead Breeding Blanket nuclear response	56
Influence of PbLi hydraulic path and integration layout on MHD pressure losses	56
Post-test analysis of SHRT45R transient performed on the EBR-II FR	55
System thermal-hydraulic modelling of the phénix dissymmetric test benchmark	55
The demo water-cooled lead–lithium breeding blanket: Design status at the end of the pre-conceptual design phase	55
Qualification of a RELAP5-3D © system code nodalization of EBR-II	54
Validation of the 1D+2D thermal-hydraulic module of the FRENETIC code	54
Supporto alla progettazione del combustibile nucleare per il reattore LFR	54
EBR-II passive safety demonstration tests benchmark analyses-phase 2	54
Pre-conceptual design of EU DEMO balance of plant systems: Objectives and challenges	53
Design of a Prototypical Mock-Up for the Experimental Investigation of WCLL First-Wall Performances	53
Caratterizzazione sperimentale dell'interazione metallo liquido pesante - acqua e qualifica rottura generatore di vapore LFR	53
Installazione della sezione di prova Hero nella facility Circe: sviluppo nodalizzazione e progettazione della campagna sperimentale	53
On the effect of stiffening plates configuration on the DEMO Water Cooled Lithium Lead Breeding Blanket module thermo-mechanical behaviour	53
Investigation of the DEMO WCLL Breeding Blanket Cooling Water Activation	53
IAEA's coordinated research project on EBR-II Shutdown heat removal tests	52
Validazione e analisi dei gas di fissione in combustibili MOX ad elevato burnup	52
Experimental analysis of stationary and transient scenarios of alfred steam generator bayonet tube in circe-hero facility	51
MHD pressure drop estimate for the WCLL in-magnet PbLi loop	51
Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System	50
Investigation of heat transfer in a steam generator bayonet tube for the development of PbLi technology for EU DEMO fusion reactor	50
Preliminary Thermo-Mechanical Design of the Once through Steam Generator and Molten Salt Intermediate Heat Exchanger for EU DEMO	50
Systems engineering activities supporting the heating & current drive and fuelling lines systems integration in the European DEMO breeding blanket	49
Thermal-hydraulic and thermo-mechanical simulations of Water-Heavy Liquid Metal interactions towards the DEMO WCLL breeding blanket design	49
MHD forced convection flow in dielectric and electro-conductive rectangular annuli	49
Hybrid 1D + 2D modelling for the assessment of the heat transfer in the EU DEMO water-cooled lithium-lead manifolds	49
Experimental investigation and SIMMER-III code modelling of LBE-water interaction in LIFUS5/Mod2 facility	48
Parametric thermal analysis for the optimization of Double Walled Tubes layout in the Water Cooled Lithium Lead inboard blanket of DEMO fusion reactor	48
Qualifica di codici di calcolo dedicati alle analisi di sistema avanzati quando applicati nella simulazione di impianti a metallo liquido	47
Experimental and numerical results of LIFUS5/Mod3 series E test on in-box LOCA transient for WCLL-BB	46
Preliminary design of a helical coil steam generator mock-up for the CIRCE facility for the development of DEMO LiPb heat exchanger	44
Thermo-hydraulic analysis of PbLi ancillary system of WCLL TBM undergoing in-box LOCA	44
Thermal-hydraulic code-to-code benchmark in a simplified EBR-II geometry	43
Totale	6.878

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Categoria	#
all - tutte	52.411
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	52.411

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2019/2020	161	0	0	0	0	8	17	47	15	11	23	17	23
2020/2021	1.057	13	19	10	19	172	10	24	99	86	123	346	136
2021/2022	1.323	39	320	55	75	154	33	63	271	82	25	71	135
2022/2023	2.576	191	478	182	372	98	433	44	227	330	83	69	69
2023/2024	1.822	109	69	201	44	145	350	97	155	114	148	128	262
2024/2025	635	75	396	114	50	0	0	0	0	0	0	0	0
Totale													7.574