statistiche ricercatore

DEL NEVO, ALESSANDRO

Distribuzione geografica

Continente	#
EU - Europa	12.046
NA - Nord America	10.887
AS - Asia	5.739
SA - Sud America	918
Continente sconosciuto - Info sul continente non disponibili	296
AF - Africa	164
OC - Oceania	16
Totale	30.066

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Nazione	#
US - Stati Uniti d'America	10.399
RU - Federazione Russa	6.853
SG - Singapore	2.418
CN - Cina	1.719
IT - Italia	1.508
DE - Germania	1.077
BR - Brasile	752
GB - Regno Unito	637
SE - Svezia	544
FI - Finlandia	415
VN - Vietnam	385
FR - Francia	384
CA - Canada	383
HK - Hong Kong	361
JP - Giappone	201
KR - Corea	146
NL - Olanda	141
IN - India	115
MA - Marocco	101
BD - Bangladesh	98
PL - Polonia	75
BE - Belgio	74
AT - Austria	73
ES - Italia	61
AR - Argentina	56
MX - Messico	52
CO - Colombia	36
IQ - Iraq	35
TR - Turchia	31
ZA - Sudafrica	31
UA - Ucraina	29
CH - Svizzera	25
PK - Pakistan	25
UZ - Uzbekistan	24
EC - Ecuador	23
GR - Grecia	23
ID - Indonesia	21
RO - Romania	21
LT - Lituania	20
VE - Venezuela	19
PH - Filippine	17
EU - Europa	15
HU - Ungheria	14
CZ - Repubblica Ceca	13
JM - Giamaica	13
AE - Emirati Arabi Uniti	12
AU - Australia	12
JO - Giordania	12
MY - Malesia	12
KZ - Kazakistan	11
TH - Thailandia	11
AZ - Azerbaigian	10
CR - Costa Rica	10
AL - Albania	9
CL - Cile	9
IR - Iran	9
NP - Nepal	9
SA - Arabia Saudita	9
TN - Tunisia	9
IL - Israele	8
PA - Panama	8
SK - Slovacchia (Repubblica Slovacca)	8
IE - Irlanda	7
OM - Oman	7
PT - Portogallo	7
PY - Paraguay	7
TW - Taiwan	7
GE - Georgia	6
RS - Serbia	6
AM - Armenia	5
BO - Bolivia	5
LB - Libano	5
LV - Lettonia	5
PE - Perù	5
UY - Uruguay	5
DO - Repubblica Dominicana	4
EG - Egitto	4
SV - El Salvador	4
BZ - Belize	3
DZ - Algeria	3
ET - Etiopia	3
IS - Islanda	3
KE - Kenya	3
TT - Trinidad e Tobago	3
XK - ???statistics.table.value.countryCode.XK???	3
DK - Danimarca	2
GA - Gabon	2
HN - Honduras	2
HR - Croazia	2
KW - Kuwait	2
LU - Lussemburgo	2
MD - Moldavia	2
MT - Malta	2
NG - Nigeria	2
NI - Nicaragua	2
NZ - Nuova Zelanda	2
PS - Palestinian Territory	2
SI - Slovenia	2
AO - Angola	1
BA - Bosnia-Erzegovina	1
Totale	29.769

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Città	#
Dallas	3.182
Moscow	1.530
Chandler	1.181
San Jose	1.089
Singapore	1.048
Ashburn	795
Munich	446
Santa Clara	429
Hefei	394
Council Bluffs	324
Hong Kong	308
Boardman	298
Toronto	295
Beijing	289
San Mateo	285
Southend	267
Hamburg	261
Helsinki	251
New York	222
Los Angeles	189
Rome	164
The Dalles	155
Seoul	130
Berlin	110
Lauterbourg	108
Milan	108
Ho Chi Minh City	104
Lappeenranta	103
Phoenix	96
Casablanca	87
São Paulo	81
Hanoi	77
Turin	76
Columbus	68
Miami	67
Shanghai	64
Las Vegas	63
Brussels	61
Orem	59
Tokyo	59
Dong Ket	58
Marseille	57
Guangzhou	55
Falkenstein	54
Amsterdam	52
Warsaw	51
Vienna	48
Bologna	47
Frankfurt am Main	43
Paris	43
Chicago	42
Montreal	39
Redwood City	39
Ann Arbor	38
Denver	35
Stockholm	34
Turku	34
Washington	34
Nuremberg	33
Chennai	31
Mountain View	30
Brooklyn	29
London	28
Trenton	27
Manchester	26
Poplar	26
Atlanta	24
Pisa	24
Johannesburg	23
Tashkent	22
Central	21
Boston	20
Belo Horizonte	19
Rio de Janeiro	19
Jülich	18
Da Nang	17
Mazzano Romano	17
San Francisco	17
Shenzhen	17
Tortona	17
Wilmington	17
Genoa	16
Houston	16
Lyon	16
Jyväskylä	15
Naples	15
Venice	14
Baghdad	12
Campinas	12
Falls Church	12
Fortaleza	12
Haiphong	12
Jinan	12
Mexico City	12
Qingdao	12
Richardson	12
Amman	11
Mumbai	11
Serra	11
Xi'an	11
Totale	16.492

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Nome	#
Assessment of the relevancy of ENEA Water Loop facility with respect to ITER WCLL TBS Water Cooling System by considering their thermal-hydraulic performances	1.058
Divertor Tokamak Test facility project: status of design and implementation	437
Overview on lead-cooled fast reactor design and related technologies development in ENEA	429
ALFRED-SGBT. Preliminary characterization by the HERO test section	399
Assessment of SIMMER-III code in predicting water cooled lithium lead breeding blanket “in-box-Loss of Coolant Accident”	388
Coupled simulations of natural and forced circulation tests in Nacie facility using relap5 and Ansys fluent codes	388
Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment	370
Caratterizzazione sperimentale dell'interazione metallo liquido pesante - acqua e qualifica rottura generatore di vapore LFR	368
Analisi di pre-test della campagna sperimentale CIRCE/HERO con codici di sistema	361
Fusion technologies development at ENEA Brasimone Research Centre: Status and perspectives	360
Raccolta delle relazioni di partecipazione ai comitati e gruppi internazionali sul nucIeare da fissione	352
Experimental campaign in support of the safety studies of the STGR in LFR	350
Characterization of leak detection in HLM system using LIFUS5/MOD3 facility	343
Pre-test analysis of thermal-hydraulic behaviour of the NACIE facility for the characterization of a fuel pin bundle	325
Status of Pb-16Li technologies for European DEMO fusion reactor	325
Analisi del comportamento del combustibile MOX ad elevato burnup in condizioni di normal operation e DBA	322
Activities in Support to the Assessment of Steam Generator Bayonet Tubes, for GEN-IV Applications	310
CIRCE experimental set-up design and test matrix definition	301
GEN-IV LFR development: Status & perspectives	282
ALFRED-SGBT. Preliminary characterization by the HERO test section	280
Experimental investigation in LIFUS5/Mod2 facility of spiral-tube steam Generator Rupture scenarios for ELFR	278
Development and validation of an approach and numerical models for safety analysis of FBR	268
Development of best estimate numerical tools for LFR design and safety analysis	267
Advancement in FGR modeling for transient analysis of FR fuel	265
Modeling and analysis of nuclear fuel pin behavior for innovative lead cooled FBR	261
Development of best estimate numerical tools for LFR design and safety analysis (2018)	260
Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System	255
Optimization of the first wall cooling system for the DEMO WCLL blanket	255
Alternative design of DEMO Water Cooled Lithium Lead internal structure	253
DEMO port plug design and integration studies	251
Benchmark and preliminary validation of the thermal-hydraulic module of the FRENETIC code against EBR-II data	249
Assessment of DEMO WCLL breeding blanket primary heat transfer system isolation valve absorbed doses due to activated water	249
Thermal-hydraulic modeling and analysis of the Water Cooling System for the ITER Test Blanket Module	249
Development of best estimate numerical tools for LFR design and safety analysis	246
Investigation on cooling performance of WCLL breeding blanket first wall for EU DEMO	245
Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project	237
Progettazione e implementazione di un sistema per la rilevazione di piccole perdite. Design and follow-up of a LBE/water leakage detection system	235
Development of a SIMMERRELAP5 coupling tool	235
Assessment of SIMMER-III code based on steam generator tube rupture experiments in LIFUS5/Mod2 facility	235
W-HYDRA: a new experimental platform for the Water-Cooled Lead Lithium Breeding Blanket	234
Design of a Prototypical Mock-Up for the Experimental Investigation of WCLL First-Wall Performances	232
Test di caratterizzazione sperimentale del sistema per la rilevazione di piccole perdite nel Generatore di Vapore LFR	232
Pre-conceptual design of EU DEMO balance of plant systems: Objectives and challenges	230
Test di caratterizzazione sperimentale del sistema per la rilevazione di piccole perdite nel Generatore di Vapore LFR	229
Parametric study of the influence of double-walled tubes layout on the DEMO WCLL breeding blanket thermal performances	228
Analysis of the thermal-hydraulic behavior of the EU-DEMO WCLL breeding blanket cooling systems during a loss of flow accident	227
Post-test of the sgtr experimental tests carried out in the LIFUS facility	224
Maturation of critical technologies for the DEMO balance of plant systems	223
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	223
Development of a model for the thermal-hydraulic characterization of the He-FUS3 loop	222
Parametric thermal-hydraulic analysis of the EU DEMO Water-Cooled Lithium-Lead First Wall using the GETTHEM code	221
Design dell’esperimento e specifica tecnica di fornitura relativa all’up-grade dell’impianto LIFUS5/Mod2	220
Experimental investigation of spiral tubes steam generator rupture scenarios in LIFUS5/MOD2 facility for ELFR	219
Design and preliminary analyses of the new Water Cooled Lithium Lead TBM for ITER	219
Qualification of TRACE V5.0 code against fast cooldown transient in the pkl-iii integral test facility	218
Hero test section for experimental investigation of steam generator bayonet tube of ALFRED	218
Thermal-hydraulic modeling and analyses of the water-cooled EU DEMO using RELAP5 system code	218
On the impact of the heat transfer modelling approach on the prediction of EU-DEMO WCLL breeding blanket thermal performances	218
Test Series D experimental results for SIMMER code validation of WCLL BB in-box LOCA in LIFUS5/Mod3 facility	217
Experimental Characterization of Leak Detection Systems in HLM Pool Using LIFUS5/Mod3 Facility	217
On the effect of stiffening plates configuration on the DEMO Water Cooled Lithium Lead Breeding Blanket module thermo-mechanical behaviour	216
Experimental and numerical investigations of interaction between heavy liquid metal and water for supporting the safety of LFR GEN. IV reator design	215
Qualification of a RELAP5-3D © system code nodalization of EBR-II	214
RELAP5/SIMMER-III code coupling development for PbLi-water interaction	214
Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment	214
Nuclear performances of the water-cooled lithium lead DEMO reactor: Neutronic analysis on a fully heterogeneous model	211
Sviluppo e validazione di un approccio e di modelli per le analisi di sicurezza di reattori veloci di IV generazione	210
MHD issues related to the use of Lithium Lead eutectic as breeder material for blankets of fusion power plants	208
Post-test analysis of SHRT45R transient performed on the EBR-II FR	208
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications	206
Nuclear analysis of the Water cooled lithium lead DEMO reactor	206
Preliminary design of the top cap of DEMO Water-Cooled Lithium Lead breeding blanket segments	205
EBR-II passive safety demonstration tests benchmark analyses-phase 2	204
Preliminary analysis of an in-box LOCA in the breeding unit of the WCLL TBM for the ITER reactor with SIMMER-IV code	203
Development of a PbLi heat exchanger for EU DEMO fusion reactor: Experimental test and system code assessment	202
Thermo-hydraulic analysis of EU DEMO WCLL breeding blanket	202
Steam Generator mock-up preliminary design suitable for Pb-Li technology demonstration and code assessment	202
Preliminary system modeling for the EUROfusion water cooled lithium lead blanket	199
Experimental Results of PbLi-Water Reaction Performed in LIFUS5/Mod3 Separate Effect Test Facility	197
System thermal-hydraulic modelling of the phénix dissymmetric test benchmark	197
Investigation of heat transfer in a steam generator bayonet tube for the development of PbLi technology for EU DEMO fusion reactor	197
Experimental and numerical results of LIFUS5/Mod3 series E test on in-box LOCA transient for WCLL-BB	196
Parametric thermal analysis for the optimization of Double Walled Tubes layout in the Water Cooled Lithium Lead inboard blanket of DEMO fusion reactor	195
Experimental investigation on circe-hero for the eu demo pbli/water heat exchanger development	193
Simulation study of pressure trends in the case of loss of coolant accident in Water Cooled Lithium Lead blanket module	193
Parametric study of the influence of First Wall cooling water on the Water Cooled Lithium Lead Breeding Blanket nuclear response	193
Investigation of the DEMO WCLL Breeding Blanket Cooling Water Activation	193
Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems	192
Influence of PbLi hydraulic path and integration layout on MHD pressure losses	191
IAEA's coordinated research project on EBR-II Shutdown heat removal tests	188
Development of the neutronic module and benchmark and validation of the thermal-hydraulic module of the FRENETIC code	188
Thermal-hydraulic and thermo-mechanical simulations of Water-Heavy Liquid Metal interactions towards the DEMO WCLL breeding blanket design	188
RELAP5-3D three-dimensional analysis based on Phénix dissymmetric transient test	187
MHD mixed convection flow in the WCLL: Heat transfer analysis and cooling system optimization	186
MHD pressure drop estimate for the WCLL in-magnet PbLi loop	185
Systems engineering activities supporting the heating & current drive and fuelling lines systems integration in the European DEMO breeding blanket	184
Preliminary design of a helical coil steam generator mock-up for the CIRCE facility for the development of DEMO LiPb heat exchanger	183
Installazione della sezione di prova Hero nella facility Circe: sviluppo nodalizzazione e progettazione della campagna sperimentale	183
Validation of the 1D+2D thermal-hydraulic module of the FRENETIC code	182
Updated design of water-cooled breeder blanket for CFETR	182
Totale	25.142

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Categoria	#
all - tutte	117.118
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	117.118

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2021/2022	964	0	0	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	11.121	75	396	114	169	543	446	661	601	692	341	2.948	4.135
2025/2026	11.333	1.146	2.445	2.256	1.018	769	638	1.172	630	304	508	314	133
2026/2027	673	177	412	84	0	0	0	0	0	0	0	0	0
Totale													30.066