statistiche ricercatore

MORO, FABIO

Distribuzione geografica

Continente	#
NA - Nord America	1.476
EU - Europa	1.247
AS - Asia	159
Continente sconosciuto - Info sul continente non disponibili	5
AF - Africa	1
Totale	2.888

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Nazione	#
US - Stati Uniti d'America	1.374
IT - Italia	460
GB - Regno Unito	215
SE - Svezia	188
AT - Austria	123
CN - Cina	103
CA - Canada	102
DE - Germania	99
FI - Finlandia	41
BE - Belgio	40
FR - Francia	39
HK - Hong Kong	30
IN - India	24
SI - Slovenia	9
NL - Olanda	6
EU - Europa	5
CH - Svizzera	4
ES - Italia	4
RU - Federazione Russa	4
CZ - Repubblica Ceca	3
GR - Grecia	3
RO - Romania	3
UA - Ucraina	2
CI - Costa d'Avorio	1
IE - Irlanda	1
IR - Iran	1
LT - Lituania	1
PL - Polonia	1
RS - Serbia	1
SG - Singapore	1
Totale	2.888

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Città	#
Chandler	604
Rome	146
Ashburn	114
San Mateo	108
Toronto	101
New York	98
Southend	95
Vienna	82
Beijing	52
Berlin	52
Boardman	49
Trenton	42
Brussels	40
Helsinki	37
Hong Kong	30
Milan	19
Ann Arbor	18
Las Vegas	18
Los Angeles	16
Mazzano Romano	14
Bologna	13
Canale Monterano	9
Mountain View	9
Chicago	8
Frosinone	8
Ciampino	7
Vanzaghello	7
Miami	6
Redwood City	6
Didcot	5
Knoxville	5
Padova	5
Pomarance	5
Redmond	5
Como	4
Karlsruhe	4
Lido degli Estensi	4
Ljubljana	4
Mumbai	4
Arlington	3
Bracciano	3
Castel Gandolfo	3
Ferrara	3
Frankfurt am Main	3
Hanover	3
Madrid	3
Marseille	3
Paris	3
Pontedassio	3
Turin	3
Épalinges	3
Angri	2
Arona	2
Busto Arsizio	2
Cagliari	2
Capannori	2
Cassino	2
Castellana Grotte	2
Chengdu	2
Eggenstein-Leopoldshafen	2
Everett	2
Freising	2
Genoa	2
Guangzhou	2
Huizen	2
Lappeenranta	2
London	2
L’Aquila	2
Napoli	2
Piglio	2
Quargnento	2
Rockville	2
Saint-Fons	2
Stockholm	2
Timisoara	2
Vicenza	2
Vignola	2
Abidjan	1
Anzio	1
Ardea	1
Bangalore	1
Bordeaux	1
Borås	1
Brno	1
Catania	1
Chennai	1
Cisterna di Latina	1
Desio	1
Dublin	1
Esslingen am Neckar	1
Falkenstein	1
Ferentino	1
Figueroles	1
Florence	1
Forano	1
Fuzhou	1
Garching	1
Geislingen an der Steige	1
Geneva	1
Grafenhausen	1
Totale	1.964

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Nome	#
SORGENTINA-RF project: fusion neutrons for 99Mo medical radioisotope	137
Calibration and test of a 6LiF-diamond detector for the HCPB mock-up experiment at JET	114
Gestione del rischio in un impianto a fusione: l’approccio integrato della radioprotezione e della sicurezza per il progetto Sorgentina-RF	91
Studi preliminari per la progettazione della schermatura della macchina a fusione Sorgentina-RF	81
Preliminary assessment of radiolysis for the cooling water system in the rotating target of SORGENTINA-RF	75
Nuclear design of Divertor Tokamak Test (DTT) facility	75
Contribution of random noise in the ITER RNC diamond neutron detectors pulses to the counting rate uncertainty	74
Neutronics studies for the novel design of lower port in DEMO	71
The deuterium-tritium fuel cycle in tokamak devices	70
Neutronics study for DTT tokamak building	70
Pre-analysis of the WCLL breeding blanket mock-up neutronics experiment at the frascati neutron generator	70
Development of the advanced D1S for shutdown dose rate calculations in fusion reactors	69
Sorgentina-RF Fusion Neutron Plant: Preliminary Design of the Bioshielding In Compliance With Dose Constraints For Workers Exposure	69
Preliminary evaluations of the environmental impact for the production of 99Mo by fusion neutrons	65
Copper benchmark experiment for the testing of JEFF-3.2 nuclear data for fusion applications	60
Activity and decay heat calculations for the European DEMO WCLL breeder blanket module including activated LiPb flow	60
Addressing the feasibility of inboard direct-line injection of high-speed pellets, for core fueling of DEMO	60
Applications of McCad for the automatic generation of MCNP 3D models in fusion neutronics	58
An active Bonner sphere spectrometer for intense neutron fields	58
Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project	57
Integral Benchmark Experiments on a Large Copper Block Using the GELINA Accelerator to Validate natCu Neutron Cross Sections from Different Neutron Cross-Sectional Databases	56
Neutronics related integration studies of EU-DEMO pellet injection system	56
High-priority prototype testing in support of system-level design development of the ITER radial neutron camera	54
Nuclear analysis of the Single Module Segment WCLL DEMO	53
Nuclear analysis of the ITER Cryopump Ports	52
Neutronic analyses and tools development efforts in the European DEMO programme	52
Results of an integration study of a diagnostics port plug in ITER	52
Neutron streaming analyses and shielding optimization through ECRH openings in DTT Tokamak building	52
Strategy and guidelines for the calibration of the ITER Radial Neutron Camera	51
Parametric study of the influence of First Wall cooling water on the Water Cooled Lithium Lead Breeding Blanket nuclear response	50
Progress in development of advanced D1S dynamic code for three-dimensional shutdown dose rate calculations	50
On the slowing-down of 14 MeV fusion neutrons: A spectrometry benchmark and perspectives on future neutron science facilities	49
Nuclear analysis of the Water cooled lithium lead DEMO reactor	49
Neutronic analyses in support of the conceptual design of the DTT tokamak radial neutron camera	48
The mcCad code for the automatic generation of MCNP 3-D models: Applications in fusion neutronics	47
Impact of the layout of the ITER Radial Neutron Camera in-port system on the measurement of the neutron emissivity profile	47
Nuclear analyses for the design of the ITER-like plasma facing components vertical targets of the DEMO divertor	45
Thermo-hydraulic modeling of the ITER radial neutron camera	45
Progress of Design and Development for the ITER Radial Neutron Camera	44
Pre-analysis of the copper neutronics benchmark experiment for nuclear data validation	44
Required, achievable and target TBR for the European DEMO	42
The demo water-cooled lead–lithium breeding blanket: Design status at the end of the pre-conceptual design phase	39
Risk Management of a Fusion Facility: Radiation Protection and Safety Integrated Approach for the Sorgentina-RF Project	37
Nuclear performances of the water-cooled lithium lead DEMO reactor: Neutronic analysis on a fully heterogeneous model	35
Nuclear analysis of ITER Test Blanket Module Port Plug	35
Shutdown dose rates at ITER equatorial ports considering radiation cross-talk from torus cryopump lower port	35
On the slowing down of 14 MeV neutrons	34
Valutazioni preliminari dell’impatto ambientale degli effluenti liquidi dovuti alla produzione di 99Mo mediante neutroni da fusione	33
Shielding proposal to reduce cross-talk from ITER lower port to equatorial port	32
Preliminary evaluations of the environmental impact for the production of 99Mo by fusion neutrons	28
Shutdown dose rate assessment with the Advanced D1S method: Development, applications and validation	28
Neutronic analyses for the equatorial diagnostic port plug #12 in ITER	27
Neutronics analysis and activation calculation for tungsten used in the DEMO divertor targets: A comparative study between the effects of WCLL and HCPB blanket, different W compositions and chromium	23
Neutronic and Shielding Analyses for the DTT Electronics	19
Development of a Novel MCNP-OSCAR Fusion Interface for the 3-D Assessment of Gamma Dose Due to the Activated Corrosion Products	19
Nuclear Analyses for the Assessment of the Loads on the ITER Radial Neutron Camera In-Port System and Evaluation of Its Measurement Performances	18
Nuclear Analyses of ITER Diagnostics Lower Ports	16
Nuclear Analysis for the Upper Ports in the NB Cell in ITER	12
A novel approach to the study of magnetohydrodynamic effect on tritium transport in WCLL breeding blanket of DEMO	7
Production and transport modelling of Po-210 in DEMO reactor	1
Totale	3.000

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Categoria	#
all - tutte	21.346
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	21.346

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2019/2020	70	0	0	0	0	0	0	46	8	0	11	2	3
2020/2021	247	0	2	0	1	62	3	3	28	23	14	103	8
2021/2022	657	7	117	6	29	51	20	77	140	79	18	44	69
2022/2023	1.333	92	273	89	208	71	210	18	97	149	43	53	30
2023/2024	693	47	23	90	26	115	167	40	89	81	15	0	0
Totale													3.000