statistiche ricercatore

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

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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

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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

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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

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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

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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	1057	13	19	10	19	172	10	24	99	86	123	346	136
2021/2022	1323	39	320	55	75	154	33	63	271	82	25	71	135
2022/2023	2596	191	478	182	372	98	433	68	242	337	96	91	8
Totale													5137