statistiche ricercatore

DEL NEVO, ALESSANDRO

Distribuzione geografica

Continente	#
EU - Europa	11.781
NA - Nord America	10.192
AS - Asia	5.605
SA - Sud America	868
AF - Africa	164
Continente sconosciuto - Info sul continente non disponibili	17
OC - Oceania	16
Totale	28.643

Salva come PNG Salva come JPEG

Nazione	#
US - Stati Uniti d'America	9.741
RU - Federazione Russa	6.852
SG - Singapore	2.413
CN - Cina	1.684
IT - Italia	1.366
DE - Germania	1.072
BR - Brasile	735
GB - Regno Unito	634
SE - Svezia	465
FI - Finlandia	415
VN - Vietnam	380
FR - Francia	374
CA - Canada	369
HK - Hong Kong	359
JP - Giappone	192
KR - Corea	146
NL - Olanda	129
IN - India	115
MA - Marocco	101
PL - Polonia	74
AT - Austria	73
BE - Belgio	73
ES - Italia	58
AR - Argentina	51
BD - Bangladesh	48
MX - Messico	45
IQ - Iraq	35
ZA - Sudafrica	31
TR - Turchia	29
UA - Ucraina	27
CH - Svizzera	25
UZ - Uzbekistan	24
GR - Grecia	23
PK - Pakistan	23
CO - Colombia	22
RO - Romania	21
LT - Lituania	20
EC - Ecuador	18
ID - Indonesia	18
EU - Europa	15
HU - Ungheria	14
CZ - Repubblica Ceca	13
AU - Australia	12
JO - Giordania	12
PH - Filippine	12
VE - Venezuela	12
AE - Emirati Arabi Uniti	11
KZ - Kazakistan	10
AL - Albania	9
AZ - Azerbaigian	9
CL - Cile	9
MY - Malesia	9
SA - Arabia Saudita	9
TN - Tunisia	9
IL - Israele	8
IR - Iran	8
JM - Giamaica	8
TH - Thailandia	8
IE - Irlanda	7
NP - Nepal	7
OM - Oman	7
PA - Panama	7
PT - Portogallo	7
PY - Paraguay	7
SK - Slovacchia (Repubblica Slovacca)	7
CR - Costa Rica	6
GE - Georgia	6
BO - Bolivia	5
TW - Taiwan	5
AM - Armenia	4
DO - Repubblica Dominicana	4
EG - Egitto	4
LB - Libano	4
LV - Lettonia	4
PE - Perù	4
RS - Serbia	4
UY - Uruguay	4
DZ - Algeria	3
ET - Etiopia	3
IS - Islanda	3
KE - Kenya	3
GA - Gabon	2
HN - Honduras	2
HR - Croazia	2
KW - Kuwait	2
LU - Lussemburgo	2
MD - Moldavia	2
NG - Nigeria	2
NZ - Nuova Zelanda	2
PS - Palestinian Territory	2
SI - Slovenia	2
SV - El Salvador	2
TT - Trinidad e Tobago	2
XK - ???statistics.table.value.countryCode.XK???	2
AO - Angola	1
BA - Bosnia-Erzegovina	1
BB - Barbados	1
BG - Bulgaria	1
BH - Bahrain	1
BS - Bahamas	1
Totale	28.624

Salva come PNG Salva come JPEG

Città	#
Dallas	3.173
Moscow	1.530
Chandler	1.180
Singapore	1.044
San Jose	1.006
Ashburn	763
Munich	446
Santa Clara	414
Hefei	394
Hong Kong	306
Boardman	297
Toronto	293
Beijing	286
San Mateo	285
Southend	267
Hamburg	261
Helsinki	251
New York	213
Los Angeles	181
The Dalles	155
Rome	154
Seoul	130
Berlin	110
Lauterbourg	108
Council Bluffs	107
Lappeenranta	103
Ho Chi Minh City	102
Milan	88
Casablanca	87
São Paulo	81
Hanoi	75
Turin	75
Columbus	67
Miami	64
Shanghai	63
Brussels	61
Las Vegas	60
Orem	59
Dong Ket	58
Marseille	56
Guangzhou	55
Falkenstein	54
Tokyo	52
Warsaw	51
Amsterdam	50
Vienna	48
Paris	43
Bologna	40
Chicago	40
Redwood City	39
Ann Arbor	38
Frankfurt am Main	38
Montreal	35
Denver	34
Stockholm	34
Turku	34
Nuremberg	33
Washington	32
Chennai	31
Mountain View	30
Brooklyn	27
London	27
Phoenix	27
Manchester	26
Poplar	26
Trenton	26
Pisa	24
Johannesburg	23
Atlanta	22
Tashkent	22
Central	21
Belo Horizonte	19
Boston	19
Jülich	18
Rio de Janeiro	18
Da Nang	17
Mazzano Romano	17
San Francisco	17
Shenzhen	17
Tortona	17
Wilmington	17
Jyväskylä	15
Houston	14
Lyon	14
Venice	14
Baghdad	12
Campinas	12
Falls Church	12
Fortaleza	12
Haiphong	12
Jinan	12
Richardson	12
Amman	11
Mumbai	11
Qingdao	11
Serra	11
Xi'an	11
Basingstoke	10
Budapest	10
Cham	10
Totale	15.937

Salva come PNG Salva come JPEG

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	1.040
Divertor Tokamak Test facility project: status of design and implementation	422
Overview on lead-cooled fast reactor design and related technologies development in ENEA	410
ALFRED-SGBT. Preliminary characterization by the HERO test section	394
Coupled simulations of natural and forced circulation tests in Nacie facility using relap5 and Ansys fluent codes	384
Assessment of SIMMER-III code in predicting water cooled lithium lead breeding blanket “in-box-Loss of Coolant Accident”	382
Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment	365
Caratterizzazione sperimentale dell'interazione metallo liquido pesante - acqua e qualifica rottura generatore di vapore LFR	363
Fusion technologies development at ENEA Brasimone Research Centre: Status and perspectives	355
Raccolta delle relazioni di partecipazione ai comitati e gruppi internazionali sul nucIeare da fissione	341
Characterization of leak detection in HLM system using LIFUS5/MOD3 facility	334
Experimental campaign in support of the safety studies of the STGR in LFR	332
Analisi di pre-test della campagna sperimentale CIRCE/HERO con codici di sistema	320
Status of Pb-16Li technologies for European DEMO fusion reactor	316
Pre-test analysis of thermal-hydraulic behaviour of the NACIE facility for the characterization of a fuel pin bundle	315
Analisi del comportamento del combustibile MOX ad elevato burnup in condizioni di normal operation e DBA	306
Activities in Support to the Assessment of Steam Generator Bayonet Tubes, for GEN-IV Applications	298
CIRCE experimental set-up design and test matrix definition	298
ALFRED-SGBT. Preliminary characterization by the HERO test section	274
GEN-IV LFR development: Status & perspectives	272
Development of best estimate numerical tools for LFR design and safety analysis	263
Development and validation of an approach and numerical models for safety analysis of FBR	261
Advancement in FGR modeling for transient analysis of FR fuel	257
Modeling and analysis of nuclear fuel pin behavior for innovative lead cooled FBR	251
Development of best estimate numerical tools for LFR design and safety analysis (2018)	251
Alternative design of DEMO Water Cooled Lithium Lead internal structure	249
Experimental investigation in LIFUS5/Mod2 facility of spiral-tube steam Generator Rupture scenarios for ELFR	247
Benchmark and preliminary validation of the thermal-hydraulic module of the FRENETIC code against EBR-II data	247
Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System	246
Optimization of the first wall cooling system for the DEMO WCLL blanket	244
Assessment of DEMO WCLL breeding blanket primary heat transfer system isolation valve absorbed doses due to activated water	243
DEMO port plug design and integration studies	241
Thermal-hydraulic modeling and analysis of the Water Cooling System for the ITER Test Blanket Module	240
Investigation on cooling performance of WCLL breeding blanket first wall for EU DEMO	239
Development of best estimate numerical tools for LFR design and safety analysis	236
Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project	232
Development of a SIMMERRELAP5 coupling tool	228
Progettazione e implementazione di un sistema per la rilevazione di piccole perdite. Design and follow-up of a LBE/water leakage detection system	227
Assessment of SIMMER-III code based on steam generator tube rupture experiments in LIFUS5/Mod2 facility	225
Parametric study of the influence of double-walled tubes layout on the DEMO WCLL breeding blanket thermal performances	225
Test di caratterizzazione sperimentale del sistema per la rilevazione di piccole perdite nel Generatore di Vapore LFR	222
Pre-conceptual design of EU DEMO balance of plant systems: Objectives and challenges	221
Design of a Prototypical Mock-Up for the Experimental Investigation of WCLL First-Wall Performances	221
Test di caratterizzazione sperimentale del sistema per la rilevazione di piccole perdite nel Generatore di Vapore LFR	220
Analysis of the thermal-hydraulic behavior of the EU-DEMO WCLL breeding blanket cooling systems during a loss of flow accident	218
Maturation of critical technologies for the DEMO balance of plant systems	216
Design dell’esperimento e specifica tecnica di fornitura relativa all’up-grade dell’impianto LIFUS5/Mod2	215
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	215
Post-test of the sgtr experimental tests carried out in the LIFUS facility	214
Parametric thermal-hydraulic analysis of the EU DEMO Water-Cooled Lithium-Lead First Wall using the GETTHEM code	213
Thermal-hydraulic modeling and analyses of the water-cooled EU DEMO using RELAP5 system code	212
Experimental Characterization of Leak Detection Systems in HLM Pool Using LIFUS5/Mod3 Facility	212
On the impact of the heat transfer modelling approach on the prediction of EU-DEMO WCLL breeding blanket thermal performances	211
Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment	211
Development of a model for the thermal-hydraulic characterization of the He-FUS3 loop	210
Test Series D experimental results for SIMMER code validation of WCLL BB in-box LOCA in LIFUS5/Mod3 facility	209
Qualification of TRACE V5.0 code against fast cooldown transient in the pkl-iii integral test facility	208
On the effect of stiffening plates configuration on the DEMO Water Cooled Lithium Lead Breeding Blanket module thermo-mechanical behaviour	208
RELAP5/SIMMER-III code coupling development for PbLi-water interaction	207
Design and preliminary analyses of the new Water Cooled Lithium Lead TBM for ITER	207
Experimental and numerical investigations of interaction between heavy liquid metal and water for supporting the safety of LFR GEN. IV reator design	206
Nuclear performances of the water-cooled lithium lead DEMO reactor: Neutronic analysis on a fully heterogeneous model	205
MHD issues related to the use of Lithium Lead eutectic as breeder material for blankets of fusion power plants	204
Hero test section for experimental investigation of steam generator bayonet tube of ALFRED	203
Experimental investigation of spiral tubes steam generator rupture scenarios in LIFUS5/MOD2 facility for ELFR	203
Sviluppo e validazione di un approccio e di modelli per le analisi di sicurezza di reattori veloci di IV generazione	201
Nuclear analysis of the Water cooled lithium lead DEMO reactor	200
W-HYDRA: a new experimental platform for the Water-Cooled Lead Lithium Breeding Blanket	198
Preliminary design of the top cap of DEMO Water-Cooled Lithium Lead breeding blanket segments	198
Steam Generator mock-up preliminary design suitable for Pb-Li technology demonstration and code assessment	198
Development of a PbLi heat exchanger for EU DEMO fusion reactor: Experimental test and system code assessment	195
EBR-II passive safety demonstration tests benchmark analyses-phase 2	195
Investigation of heat transfer in a steam generator bayonet tube for the development of PbLi technology for EU DEMO fusion reactor	194
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications	193
Preliminary system modeling for the EUROfusion water cooled lithium lead blanket	192
System thermal-hydraulic modelling of the phénix dissymmetric test benchmark	191
Experimental and numerical results of LIFUS5/Mod3 series E test on in-box LOCA transient for WCLL-BB	191
Preliminary analysis of an in-box LOCA in the breeding unit of the WCLL TBM for the ITER reactor with SIMMER-IV code	190
Experimental investigation on circe-hero for the eu demo pbli/water heat exchanger development	189
Post-test analysis of SHRT45R transient performed on the EBR-II FR	189
Simulation study of pressure trends in the case of loss of coolant accident in Water Cooled Lithium Lead blanket module	188
Parametric study of the influence of First Wall cooling water on the Water Cooled Lithium Lead Breeding Blanket nuclear response	188
Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems	187
Investigation of the DEMO WCLL Breeding Blanket Cooling Water Activation	187
Influence of PbLi hydraulic path and integration layout on MHD pressure losses	186
Qualification of a RELAP5-3D © system code nodalization of EBR-II	185
Parametric thermal analysis for the optimization of Double Walled Tubes layout in the Water Cooled Lithium Lead inboard blanket of DEMO fusion reactor	185
IAEA's coordinated research project on EBR-II Shutdown heat removal tests	184
Development of the neutronic module and benchmark and validation of the thermal-hydraulic module of the FRENETIC code	184
Thermal-hydraulic and thermo-mechanical simulations of Water-Heavy Liquid Metal interactions towards the DEMO WCLL breeding blanket design	184
MHD mixed convection flow in the WCLL: Heat transfer analysis and cooling system optimization	184
RELAP5-3D three-dimensional analysis based on Phénix dissymmetric transient test	184
Thermo-hydraulic analysis of EU DEMO WCLL breeding blanket	183
Experimental Results of PbLi-Water Reaction Performed in LIFUS5/Mod3 Separate Effect Test Facility	182
MHD pressure drop estimate for the WCLL in-magnet PbLi loop	181
Systems engineering activities supporting the heating & current drive and fuelling lines systems integration in the European DEMO breeding blanket	180
Preliminary design of a helical coil steam generator mock-up for the CIRCE facility for the development of DEMO LiPb heat exchanger	179
Updated design of water-cooled breeder blanket for CFETR	179
Validation of the 1D+2D thermal-hydraulic module of the FRENETIC code	177
Installazione della sezione di prova Hero nella facility Circe: sviluppo nodalizzazione e progettazione della campagna sperimentale	176
Totale	24.241

Salva come PNG Salva come JPEG

Categoria	#
all - tutte	107.937
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	107.937

Salva come PNG Salva come JPEG

	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2020/2021	605	0	0	0	0	0	0	0	0	0	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	11.121	75	396	114	169	543	446	661	601	692	341	2.948	4.135
2025/2026	10.855	1.146	2.445	2.256	1.018	769	638	1.172	630	304	477	0	0
Totale													28.915