statistiche ricercatore

DEL NEVO, ALESSANDRO

Distribuzione geografica

Continente	#
NA - Nord America	4.175
EU - Europa	4.152
AS - Asia	1.793
SA - Sud America	553
AF - Africa	33
Continente sconosciuto - Info sul continente non disponibili	17
OC - Oceania	10
Totale	10.733

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Nazione	#
US - Stati Uniti d'America	3.854
IT - Italia	1.076
DE - Germania	944
CN - Cina	730
GB - Regno Unito	516
SG - Singapore	513
BR - Brasile	495
SE - Svezia	436
FI - Finlandia	371
CA - Canada	299
RU - Federazione Russa	296
HK - Hong Kong	290
FR - Francia	167
BE - Belgio	69
NL - Olanda	67
AT - Austria	66
VN - Vietnam	59
IN - India	47
JP - Giappone	26
GR - Grecia	23
AR - Argentina	21
CH - Svizzera	21
RO - Romania	17
EU - Europa	15
UA - Ucraina	15
CO - Colombia	12
PK - Pakistan	12
TR - Turchia	12
ES - Italia	11
HU - Ungheria	11
MA - Marocco	11
UZ - Uzbekistan	11
IQ - Iraq	10
KR - Corea	10
KZ - Kazakistan	9
PL - Polonia	9
CZ - Repubblica Ceca	8
MX - Messico	8
ZA - Sudafrica	8
AU - Australia	7
AZ - Azerbaigian	7
BD - Bangladesh	7
EC - Ecuador	7
JO - Giordania	7
VE - Venezuela	7
IR - Iran	6
TH - Thailandia	6
TN - Tunisia	6
AL - Albania	5
IE - Irlanda	5
JM - Giamaica	5
OM - Oman	5
PT - Portogallo	5
CL - Cile	4
IL - Israele	4
PA - Panama	4
SK - Slovacchia (Repubblica Slovacca)	4
AE - Emirati Arabi Uniti	3
NP - Nepal	3
PY - Paraguay	3
AM - Armenia	2
BO - Bolivia	2
CR - Costa Rica	2
DO - Repubblica Dominicana	2
DZ - Algeria	2
EG - Egitto	2
GE - Georgia	2
IS - Islanda	2
KW - Kuwait	2
LB - Libano	2
LT - Lituania	2
LV - Lettonia	2
NZ - Nuova Zelanda	2
PE - Perù	2
SA - Arabia Saudita	2
TW - Taiwan	2
XK - ???statistics.table.value.countryCode.XK???	2
AO - Angola	1
DK - Danimarca	1
GA - Gabon	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
Totale	10.733

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Città	#
Chandler	1.180
Munich	374
Santa Clara	372
Boardman	294
San Mateo	285
Toronto	281
Ashburn	267
Southend	267
Hamburg	261
Helsinki	245
Hong Kong	241
Singapore	141
New York	139
Beijing	125
Rome	121
Berlin	109
Lappeenranta	102
Los Angeles	79
Milan	67
Miami	63
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
Washington	32
Mountain View	30
Nuremberg	29
São Paulo	29
Council Bluffs	28
Bologna	27
Trenton	26
Pisa	22
Central	21
Amsterdam	19
Frankfurt am Main	17
Mazzano Romano	17
Tortona	17
Wilmington	17
Belo Horizonte	16
Tokyo	16
Jyväskylä	15
The Dalles	15
Chicago	14
Lyon	14
Falls Church	12
Paris	12
Richardson	12
Shenzhen	12
Qingdao	11
Cham	10
Düsseldorf	10
Rio de Janeiro	10
Serra	10
Tashkent	10
Budapest	9
Lucca	9
Redmond	9
Xian	9
Borås	8
Bucharest	8
Campinas	8
Fortaleza	8
London	8
Neive	8
Ribeirão Preto	8
San Nicola	8
St Petersburg	8
Venice	8
Bra	7
Darien	7
Ferrara	7
Florence	7
Santo André	7
Stockholm	7
Zhengzhou	7
Amman	6
Baku	6
Brasília	6
Chongqing	6
Curitiba	6
Genoa	6
Jinan	6
Nanjing	6
Padova	6
Palermo	6
Pavia	6
Almaty	5
Bergamo	5
Boydton	5
Central District	5
Chengdu	5
Goiânia	5
Guarulhos	5
Totale	6.375

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Nome	#
ALFRED-SGBT. Preliminary characterization by the HERO test section	221
Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment	220
Coupled simulations of natural and forced circulation tests in Nacie facility using relap5 and Ansys fluent codes	218
Assessment of SIMMER-III code in predicting water cooled lithium lead breeding blanket “in-box-Loss of Coolant Accident”	212
Caratterizzazione sperimentale dell'interazione metallo liquido pesante - acqua e qualifica rottura generatore di vapore LFR	209
Overview on lead-cooled fast reactor design and related technologies development in ENEA	190
Experimental campaign in support of the safety studies of the STGR in LFR	180
Pre-test analysis of thermal-hydraulic behaviour of the NACIE facility for the characterization of a fuel pin bundle	172
Characterization of leak detection in HLM system using LIFUS5/MOD3 facility	171
Status of Pb-16Li technologies for European DEMO fusion reactor	165
Raccolta delle relazioni di partecipazione ai comitati e gruppi internazionali sul nucIeare da fissione	149
GEN-IV LFR development: Status & perspectives	147
Optimization of the first wall cooling system for the DEMO WCLL blanket	138
Analisi del comportamento del combustibile MOX ad elevato burnup in condizioni di normal operation e DBA	134
Fusion technologies development at ENEA Brasimone Research Centre: Status and perspectives	134
Modeling and analysis of nuclear fuel pin behavior for innovative lead cooled FBR	133
Development of best estimate numerical tools for LFR design and safety analysis	124
CIRCE experimental set-up design and test matrix definition	121
Development and validation of an approach and numerical models for safety analysis of FBR	121
Analisi di pre-test della campagna sperimentale CIRCE/HERO con codici di sistema	116
Development of best estimate numerical tools for LFR design and safety analysis (2018)	112
Post-test of the sgtr experimental tests carried out in the LIFUS facility	110
Development of best estimate numerical tools for LFR design and safety analysis	108
Benchmark and preliminary validation of the thermal-hydraulic module of the FRENETIC code against EBR-II data	107
Experimental investigation in LIFUS5/Mod2 facility of spiral-tube steam Generator Rupture scenarios for ELFR	106
Advancement in FGR modeling for transient analysis of FR fuel	106
Activities in Support to the Assessment of Steam Generator Bayonet Tubes, for GEN-IV Applications	105
Experimental and numerical investigations of interaction between heavy liquid metal and water for supporting the safety of LFR GEN. IV reator design	103
DEMO port plug design and integration studies	100
Thermal-hydraulic modeling and analyses of the water-cooled EU DEMO using RELAP5 system code	98
Progettazione e implementazione di un sistema per la rilevazione di piccole perdite. Design and follow-up of a LBE/water leakage detection system	97
RELAP5-3D three-dimensional analysis based on Phénix dissymmetric transient test	97
Design and preliminary analyses of the new Water Cooled Lithium Lead TBM for ITER	96
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications	95
MHD issues related to the use of Lithium Lead eutectic as breeder material for blankets of fusion power plants	94
Experimental investigation of spiral tubes steam generator rupture scenarios in LIFUS5/MOD2 facility for ELFR	94
Preliminary system modeling for the EUROfusion water cooled lithium lead blanket	93
Test di caratterizzazione sperimentale del sistema per la rilevazione di piccole perdite nel Generatore di Vapore LFR	91
ALFRED-SGBT. Preliminary characterization by the HERO test section	91
Investigation on cooling performance of WCLL breeding blanket first wall for EU DEMO	91
Alternative design of DEMO Water Cooled Lithium Lead internal structure	89
Parametric study of the influence of double-walled tubes layout on the DEMO WCLL breeding blanket thermal performances	89
Test Series D experimental results for SIMMER code validation of WCLL BB in-box LOCA in LIFUS5/Mod3 facility	87
Assessment of DEMO WCLL breeding blanket primary heat transfer system isolation valve absorbed doses due to activated water	87
Test di caratterizzazione sperimentale del sistema per la rilevazione di piccole perdite nel Generatore di Vapore LFR	86
Development of a SIMMERRELAP5 coupling tool	86
Steam Generator mock-up preliminary design suitable for Pb-Li technology demonstration and code assessment	86
Thermal-hydraulic modeling and analysis of the Water Cooling System for the ITER Test Blanket Module	86
Qualification of TRACE V5.0 code against fast cooldown transient in the pkl-iii integral test facility	85
Divertor Tokamak Test facility project: status of design and implementation	84
Experimental Characterization of Leak Detection Systems in HLM Pool Using LIFUS5/Mod3 Facility	84
Parametric thermal-hydraulic analysis of the EU DEMO Water-Cooled Lithium-Lead First Wall using the GETTHEM code	83
Development of the neutronic module and benchmark and validation of the thermal-hydraulic module of the FRENETIC code	83
On the impact of the heat transfer modelling approach on the prediction of EU-DEMO WCLL breeding blanket thermal performances	83
RELAP5/SIMMER-III code coupling development for PbLi-water interaction	82
Assessment of SIMMER-III code based on steam generator tube rupture experiments in LIFUS5/Mod2 facility	82
Design dell’esperimento e specifica tecnica di fornitura relativa all’up-grade dell’impianto LIFUS5/Mod2	81
Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project	81
Simulation study of pressure trends in the case of loss of coolant accident in Water Cooled Lithium Lead blanket module	80
Pre-conceptual design of EU DEMO balance of plant systems: Objectives and challenges	79
Development of a model for the thermal-hydraulic characterization of the He-FUS3 loop	78
Thermal-hydraulic analysis of the DEMO WCLL elementary cell: BZ tubes layout optimization	78
Sviluppo e validazione di un approccio e di modelli per le analisi di sicurezza di reattori veloci di IV generazione	77
Investigation of heat transfer in a steam generator bayonet tube for the development of PbLi technology for EU DEMO fusion reactor	77
Nuclear analysis of the Water cooled lithium lead DEMO reactor	76
Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems	76
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	76
Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System	75
MHD mixed convection flow in the WCLL: Heat transfer analysis and cooling system optimization	75
Design of a Prototypical Mock-Up for the Experimental Investigation of WCLL First-Wall Performances	74
Thermo-hydraulic analysis of EU DEMO WCLL breeding blanket	74
Hero test section for experimental investigation of steam generator bayonet tube of ALFRED	74
Investigation of the DEMO WCLL Breeding Blanket Cooling Water Activation	74
EBR-II passive safety demonstration tests benchmark analyses-phase 2	73
Parametric study of the influence of First Wall cooling water on the Water Cooled Lithium Lead Breeding Blanket nuclear response	72
Preliminary design of the top cap of DEMO Water-Cooled Lithium Lead breeding blanket segments	72
Updated design of water-cooled breeder blanket for CFETR	72
Influence of PbLi hydraulic path and integration layout on MHD pressure losses	71
Fornitura scambiatore di calore a tubi a baionetta	70
On the effect of stiffening plates configuration on the DEMO Water Cooled Lithium Lead Breeding Blanket module thermo-mechanical behaviour	69
Deterministic safety analysis of Station Blackout postulated accident on the basis of the SMR simulator MASLWR	68
Post-test analysis of SHRT45R transient performed on the EBR-II FR	68
Supporto alla progettazione del combustibile nucleare per il reattore LFR	68
Validazione e analisi dei gas di fissione in combustibili MOX ad elevato burnup	68
Thermal-hydraulic and thermo-mechanical simulations of Water-Heavy Liquid Metal interactions towards the DEMO WCLL breeding blanket design	68
Nuclear performances of the water-cooled lithium lead DEMO reactor: Neutronic analysis on a fully heterogeneous model	67
Systems engineering activities supporting the heating & current drive and fuelling lines systems integration in the European DEMO breeding blanket	67
System thermal-hydraulic modelling of the phénix dissymmetric test benchmark	67
MHD pressure drop estimate for the WCLL in-magnet PbLi loop	67
The demo water-cooled lead–lithium breeding blanket: Design status at the end of the pre-conceptual design phase	67
Preliminary analysis of an in-box LOCA in the breeding unit of the WCLL TBM for the ITER reactor with SIMMER-IV code	66
Validation of the 1D+2D thermal-hydraulic module of the FRENETIC code	66
Installazione della sezione di prova Hero nella facility Circe: sviluppo nodalizzazione e progettazione della campagna sperimentale	66
Preliminary design of a helical coil steam generator mock-up for the CIRCE facility for the development of DEMO LiPb heat exchanger	65
Experimental investigation and SIMMER-III code modelling of LBE-water interaction in LIFUS5/Mod2 facility	65
Hybrid 1D + 2D modelling for the assessment of the heat transfer in the EU DEMO water-cooled lithium-lead manifolds	65
Preliminary Thermo-Mechanical Design of the Once through Steam Generator and Molten Salt Intermediate Heat Exchanger for EU DEMO	65
Qualification of a RELAP5-3D © system code nodalization of EBR-II	64
IAEA's coordinated research project on EBR-II Shutdown heat removal tests	63
Parametric thermal analysis for the optimization of Double Walled Tubes layout in the Water Cooled Lithium Lead inboard blanket of DEMO fusion reactor	63
Totale	9.758

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Categoria	#
all - tutte	64.756
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	64.756

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2019/2020	63	0	0	0	0	0	0	0	0	0	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	4.033	75	396	114	169	543	446	661	601	692	336	0	0
Totale													10.972