statistiche ricercatore

DEL NEVO, ALESSANDRO

Distribuzione geografica

Continente	#
EU - Europa	11.341
NA - Nord America	8.558
AS - Asia	4.775
SA - Sud America	780
AF - Africa	149
Continente sconosciuto - Info sul continente non disponibili	17
OC - Oceania	13
Totale	25.633

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Nazione	#
US - Stati Uniti d'America	8.144
RU - Federazione Russa	6.847
SG - Singapore	2.118
CN - Cina	1.530
IT - Italia	1.251
DE - Germania	1.049
BR - Brasile	680
GB - Regno Unito	593
SE - Svezia	454
FI - Finlandia	410
CA - Canada	349
HK - Hong Kong	338
FR - Francia	224
JP - Giappone	180
VN - Vietnam	153
KR - Corea	140
NL - Olanda	116
MA - Marocco	97
IN - India	85
AT - Austria	71
BE - Belgio	70
PL - Polonia	55
AR - Argentina	41
ES - Italia	39
MX - Messico	36
BD - Bangladesh	31
ZA - Sudafrica	28
CH - Svizzera	24
GR - Grecia	23
IQ - Iraq	23
TR - Turchia	22
UA - Ucraina	22
RO - Romania	18
LT - Lituania	17
UZ - Uzbekistan	17
EU - Europa	15
PK - Pakistan	14
CO - Colombia	13
ID - Indonesia	13
CZ - Repubblica Ceca	12
EC - Ecuador	12
JO - Giordania	12
HU - Ungheria	11
VE - Venezuela	11
KZ - Kazakistan	10
AU - Australia	9
AZ - Azerbaigian	9
IL - Israele	8
IR - Iran	8
TH - Thailandia	8
AE - Emirati Arabi Uniti	7
JM - Giamaica	7
SK - Slovacchia (Repubblica Slovacca)	7
TN - Tunisia	7
IE - Irlanda	6
MY - Malesia	6
OM - Oman	6
PA - Panama	6
PY - Paraguay	6
AL - Albania	5
CL - Cile	5
NP - Nepal	5
PH - Filippine	5
PT - Portogallo	5
TW - Taiwan	5
BO - Bolivia	4
CR - Costa Rica	4
DO - Repubblica Dominicana	4
GE - Georgia	4
LB - Libano	4
PE - Perù	4
SA - Arabia Saudita	4
DZ - Algeria	3
EG - Egitto	3
IS - Islanda	3
UY - Uruguay	3
AM - Armenia	2
ET - Etiopia	2
KW - Kuwait	2
LU - Lussemburgo	2
LV - Lettonia	2
MD - Moldavia	2
NG - Nigeria	2
NZ - Nuova Zelanda	2
PS - Palestinian Territory	2
TT - Trinidad e Tobago	2
XK - ???statistics.table.value.countryCode.XK???	2
AO - Angola	1
BB - Barbados	1
BG - Bulgaria	1
BH - Bahrain	1
BS - Bahamas	1
BZ - Belize	1
CI - Costa d'Avorio	1
DK - Danimarca	1
GA - Gabon	1
GD - Grenada	1
HN - Honduras	1
KE - Kenya	1
LA - Repubblica Popolare Democratica del Laos	1
Totale	25.623

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Città	#
Dallas	3.170
Moscow	1.530
Chandler	1.180
Singapore	965
Ashburn	487
Munich	445
Santa Clara	408
Hefei	393
Boardman	294
Toronto	291
Hong Kong	286
Beijing	285
San Mateo	285
Southend	267
Hamburg	261
Helsinki	248
New York	191
Los Angeles	164
Rome	142
Seoul	130
The Dalles	114
Berlin	109
Lappeenranta	102
Casablanca	86
Milan	76
São Paulo	69
Turin	67
Columbus	66
Council Bluffs	65
Miami	64
Brussels	60
Shanghai	59
Dong Ket	58
Las Vegas	58
Guangzhou	55
Falkenstein	54
Marseille	52
Vienna	48
Amsterdam	44
Tokyo	42
Redwood City	39
Ann Arbor	38
Bologna	38
Warsaw	35
Turku	34
Ho Chi Minh City	33
Washington	32
Frankfurt am Main	30
Mountain View	30
Nuremberg	30
Denver	29
Paris	26
Phoenix	26
Trenton	26
Brooklyn	25
Stockholm	25
Chicago	24
Pisa	24
Montreal	22
Central	21
Johannesburg	21
Atlanta	20
Hanoi	20
Manchester	20
Belo Horizonte	19
Boston	18
Jülich	18
London	18
Poplar	18
Chennai	17
Mazzano Romano	17
San Francisco	17
Shenzhen	17
Tortona	17
Wilmington	17
Jyväskylä	15
Orem	15
Rio de Janeiro	15
Tashkent	15
Lyon	14
Venice	14
Campinas	12
Falls Church	12
Jinan	12
Richardson	12
Amman	11
Fortaleza	11
Houston	11
Qingdao	11
Serra	11
Xi'an	11
Cham	10
Düsseldorf	10
Lucca	10
Budapest	9
Mexico City	9
Redmond	9
Ribeirão Preto	9
Seattle	9
Xian	9
Totale	13.917

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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	1.016
Divertor Tokamak Test facility project: status of design and implementation	385
ALFRED-SGBT. Preliminary characterization by the HERO test section	369
Overview on lead-cooled fast reactor design and related technologies development in ENEA	369
Coupled simulations of natural and forced circulation tests in Nacie facility using relap5 and Ansys fluent codes	361
Assessment of SIMMER-III code in predicting water cooled lithium lead breeding blanket “in-box-Loss of Coolant Accident”	359
Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment	341
Caratterizzazione sperimentale dell'interazione metallo liquido pesante - acqua e qualifica rottura generatore di vapore LFR	331
Fusion technologies development at ENEA Brasimone Research Centre: Status and perspectives	316
Raccolta delle relazioni di partecipazione ai comitati e gruppi internazionali sul nucIeare da fissione	315
Characterization of leak detection in HLM system using LIFUS5/MOD3 facility	312
Experimental campaign in support of the safety studies of the STGR in LFR	306
Status of Pb-16Li technologies for European DEMO fusion reactor	297
Pre-test analysis of thermal-hydraulic behaviour of the NACIE facility for the characterization of a fuel pin bundle	291
Analisi di pre-test della campagna sperimentale CIRCE/HERO con codici di sistema	283
Analisi del comportamento del combustibile MOX ad elevato burnup in condizioni di normal operation e DBA	276
CIRCE experimental set-up design and test matrix definition	271
Activities in Support to the Assessment of Steam Generator Bayonet Tubes, for GEN-IV Applications	262
ALFRED-SGBT. Preliminary characterization by the HERO test section	252
GEN-IV LFR development: Status & perspectives	247
Advancement in FGR modeling for transient analysis of FR fuel	238
Development of best estimate numerical tools for LFR design and safety analysis	237
Development and validation of an approach and numerical models for safety analysis of FBR	237
Development of best estimate numerical tools for LFR design and safety analysis (2018)	228
Modeling and analysis of nuclear fuel pin behavior for innovative lead cooled FBR	225
Benchmark and preliminary validation of the thermal-hydraulic module of the FRENETIC code against EBR-II data	223
Experimental investigation in LIFUS5/Mod2 facility of spiral-tube steam Generator Rupture scenarios for ELFR	222
Alternative design of DEMO Water Cooled Lithium Lead internal structure	221
Assessment of DEMO WCLL breeding blanket primary heat transfer system isolation valve absorbed doses due to activated water	221
DEMO port plug design and integration studies	220
Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System	219
Optimization of the first wall cooling system for the DEMO WCLL blanket	218
Development of best estimate numerical tools for LFR design and safety analysis	216
Investigation on cooling performance of WCLL breeding blanket first wall for EU DEMO	216
Thermal-hydraulic modeling and analysis of the Water Cooling System for the ITER Test Blanket Module	211
Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project	208
Parametric study of the influence of double-walled tubes layout on the DEMO WCLL breeding blanket thermal performances	205
Development of a SIMMERRELAP5 coupling tool	204
Progettazione e implementazione di un sistema per la rilevazione di piccole perdite. Design and follow-up of a LBE/water leakage detection system	201
Assessment of SIMMER-III code based on steam generator tube rupture experiments in LIFUS5/Mod2 facility	198
Pre-conceptual design of EU DEMO balance of plant systems: Objectives and challenges	197
Design dell’esperimento e specifica tecnica di fornitura relativa all’up-grade dell’impianto LIFUS5/Mod2	197
Design of a Prototypical Mock-Up for the Experimental Investigation of WCLL First-Wall Performances	196
Test di caratterizzazione sperimentale del sistema per la rilevazione di piccole perdite nel Generatore di Vapore LFR	194
On the impact of the heat transfer modelling approach on the prediction of EU-DEMO WCLL breeding blanket thermal performances	194
Analysis of the thermal-hydraulic behavior of the EU-DEMO WCLL breeding blanket cooling systems during a loss of flow accident	194
Thermal-hydraulic modeling and analyses of the water-cooled EU DEMO using RELAP5 system code	192
Experimental Characterization of Leak Detection Systems in HLM Pool Using LIFUS5/Mod3 Facility	192
Maturation of critical technologies for the DEMO balance of plant systems	191
Test di caratterizzazione sperimentale del sistema per la rilevazione di piccole perdite nel Generatore di Vapore LFR	191
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	191
Development of a model for the thermal-hydraulic characterization of the He-FUS3 loop	190
Parametric thermal-hydraulic analysis of the EU DEMO Water-Cooled Lithium-Lead First Wall using the GETTHEM code	189
Post-test of the sgtr experimental tests carried out in the LIFUS facility	187
Design and preliminary analyses of the new Water Cooled Lithium Lead TBM for ITER	186
Experimental and numerical investigations of interaction between heavy liquid metal and water for supporting the safety of LFR GEN. IV reator design	185
Test Series D experimental results for SIMMER code validation of WCLL BB in-box LOCA in LIFUS5/Mod3 facility	185
MHD issues related to the use of Lithium Lead eutectic as breeder material for blankets of fusion power plants	184
RELAP5/SIMMER-III code coupling development for PbLi-water interaction	184
Nuclear analysis of the Water cooled lithium lead DEMO reactor	184
Qualification of TRACE V5.0 code against fast cooldown transient in the pkl-iii integral test facility	182
Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment	182
Nuclear performances of the water-cooled lithium lead DEMO reactor: Neutronic analysis on a fully heterogeneous model	181
Experimental investigation of spiral tubes steam generator rupture scenarios in LIFUS5/MOD2 facility for ELFR	181
Steam Generator mock-up preliminary design suitable for Pb-Li technology demonstration and code assessment	181
On the effect of stiffening plates configuration on the DEMO Water Cooled Lithium Lead Breeding Blanket module thermo-mechanical behaviour	179
Preliminary design of the top cap of DEMO Water-Cooled Lithium Lead breeding blanket segments	177
Hero test section for experimental investigation of steam generator bayonet tube of ALFRED	176
Development of a PbLi heat exchanger for EU DEMO fusion reactor: Experimental test and system code assessment	175
Preliminary system modeling for the EUROfusion water cooled lithium lead blanket	175
Sviluppo e validazione di un approccio e di modelli per le analisi di sicurezza di reattori veloci di IV generazione	174
Investigation of heat transfer in a steam generator bayonet tube for the development of PbLi technology for EU DEMO fusion reactor	172
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications	171
RELAP5-3D three-dimensional analysis based on Phénix dissymmetric transient test	171
Experimental and numerical results of LIFUS5/Mod3 series E test on in-box LOCA transient for WCLL-BB	171
Simulation study of pressure trends in the case of loss of coolant accident in Water Cooled Lithium Lead blanket module	170
Investigation of the DEMO WCLL Breeding Blanket Cooling Water Activation	170
Preliminary analysis of an in-box LOCA in the breeding unit of the WCLL TBM for the ITER reactor with SIMMER-IV code	168
W-HYDRA: a new experimental platform for the Water-Cooled Lead Lithium Breeding Blanket	168
Post-test analysis of SHRT45R transient performed on the EBR-II FR	168
Parametric thermal analysis for the optimization of Double Walled Tubes layout in the Water Cooled Lithium Lead inboard blanket of DEMO fusion reactor	168
Parametric study of the influence of First Wall cooling water on the Water Cooled Lithium Lead Breeding Blanket nuclear response	167
MHD mixed convection flow in the WCLL: Heat transfer analysis and cooling system optimization	167
Experimental investigation on circe-hero for the eu demo pbli/water heat exchanger development	166
EBR-II passive safety demonstration tests benchmark analyses-phase 2	166
MHD pressure drop estimate for the WCLL in-magnet PbLi loop	166
Influence of PbLi hydraulic path and integration layout on MHD pressure losses	166
Development of the neutronic module and benchmark and validation of the thermal-hydraulic module of the FRENETIC code	164
System thermal-hydraulic modelling of the phénix dissymmetric test benchmark	164
Thermal-hydraulic and thermo-mechanical simulations of Water-Heavy Liquid Metal interactions towards the DEMO WCLL breeding blanket design	164
Thermo-hydraulic analysis of EU DEMO WCLL breeding blanket	163
Preliminary design of a helical coil steam generator mock-up for the CIRCE facility for the development of DEMO LiPb heat exchanger	162
Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems	162
Updated design of water-cooled breeder blanket for CFETR	162
Experimental Results of PbLi-Water Reaction Performed in LIFUS5/Mod3 Separate Effect Test Facility	161
Installazione della sezione di prova Hero nella facility Circe: sviluppo nodalizzazione e progettazione della campagna sperimentale	160
IAEA's coordinated research project on EBR-II Shutdown heat removal tests	159
Systems engineering activities supporting the heating & current drive and fuelling lines systems integration in the European DEMO breeding blanket	159
Qualification of a RELAP5-3D © system code nodalization of EBR-II	157
Thermal-hydraulic analysis of the DEMO WCLL elementary cell: BZ tubes layout optimization	157
Totale	21.882

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Categoria	#
all - tutte	101.955
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	101.955

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2020/2021	824	0	0	0	0	0	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	11.121	75	396	114	169	543	446	661	601	692	341	2.948	4.135
2025/2026	7.833	1.146	2.445	2.256	1.018	772	196	0	0	0	0	0	0
Totale													25.893