statistiche ricercatore

GRASSO, GIACOMO

Distribuzione geografica

Continente	#
EU - Europa	6.399
NA - Nord America	5.463
AS - Asia	2.665
SA - Sud America	440
AF - Africa	100
Continente sconosciuto - Info sul continente non disponibili	92
OC - Oceania	11
Totale	15.170

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Nazione	#
US - Stati Uniti d'America	5.189
RU - Federazione Russa	3.008
IT - Italia	1.495
SG - Singapore	1.133
CN - Cina	718
DE - Germania	464
BR - Brasile	358
GB - Regno Unito	335
SE - Svezia	305
FR - Francia	252
CA - Canada	212
HK - Hong Kong	207
VN - Vietnam	172
NL - Olanda	102
FI - Finlandia	99
JP - Giappone	96
KR - Corea	75
AT - Austria	70
BE - Belgio	70
BD - Bangladesh	61
IN - India	59
MA - Marocco	52
ES - Italia	36
PL - Polonia	34
MX - Messico	30
CH - Svizzera	29
AR - Argentina	23
TR - Turchia	19
UA - Ucraina	19
ZA - Sudafrica	16
IQ - Iraq	15
ID - Indonesia	14
RO - Romania	14
EC - Ecuador	13
CO - Colombia	12
VE - Venezuela	11
IE - Irlanda	10
LT - Lituania	10
UZ - Uzbekistan	10
EU - Europa	9
TN - Tunisia	9
TW - Taiwan	9
IL - Israele	8
JO - Giordania	8
MY - Malesia	8
PH - Filippine	8
CL - Cile	7
CZ - Repubblica Ceca	7
PK - Pakistan	7
AU - Australia	6
NI - Nicaragua	6
PE - Perù	6
HU - Ungheria	5
OM - Oman	5
PY - Paraguay	5
SV - El Salvador	5
TH - Thailandia	5
AE - Emirati Arabi Uniti	4
AL - Albania	4
DK - Danimarca	4
EE - Estonia	4
EG - Egitto	4
GR - Grecia	4
HR - Croazia	4
KZ - Kazakistan	4
NZ - Nuova Zelanda	4
SA - Arabia Saudita	4
AO - Angola	3
BO - Bolivia	3
BY - Bielorussia	3
DO - Repubblica Dominicana	3
GT - Guatemala	3
KE - Kenya	3
PS - Palestinian Territory	3
PT - Portogallo	3
TT - Trinidad e Tobago	3
BG - Bulgaria	2
CI - Costa d'Avorio	2
CR - Costa Rica	2
CY - Cipro	2
ET - Etiopia	2
HN - Honduras	2
IR - Iran	2
KG - Kirghizistan	2
LY - Libia	2
PA - Panama	2
PR - Porto Rico	2
RS - Serbia	2
SK - Slovacchia (Repubblica Slovacca)	2
UY - Uruguay	2
AM - Armenia	1
BB - Barbados	1
BF - Burkina Faso	1
BH - Bahrain	1
BN - Brunei Darussalam	1
DM - Dominica	1
GH - Ghana	1
GP - Guadalupe	1
JM - Giamaica	1
LB - Libano	1
Totale	15.075

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Città	#
Dallas	1.080
Moscow	688
Chandler	624
Singapore	542
San Jose	523
Ashburn	470
Council Bluffs	278
Rome	232
Santa Clara	195
Hefei	186
Hong Kong	174
Toronto	166
Southend	148
San Mateo	147
Boardman	134
Munich	128
Milan	125
New York	125
Hamburg	117
Beijing	109
Turin	97
The Dalles	93
Bologna	81
Helsinki	79
Phoenix	74
Los Angeles	70
Seoul	61
Berlin	58
Lauterbourg	57
Ho Chi Minh City	51
Vienna	49
Redwood City	47
Casablanca	45
Paris	42
São Paulo	38
Hanoi	37
North Tonawanda	37
Falkenstein	36
Brussels	35
Washington	32
Atlanta	31
Dong Ket	29
Columbus	28
Jülich	27
Ann Arbor	26
Genoa	26
Miami	26
Tokyo	26
Naples	25
Orem	25
Marseille	23
Montreal	23
Buffalo	22
Chicago	21
Warsaw	21
Amsterdam	20
Las Vegas	19
Belo Horizonte	18
Mountain View	18
Nuremberg	18
Dhaka	17
Frankfurt am Main	17
Guangzhou	17
Denver	16
North Bergen	16
Brooklyn	15
Shanghai	15
Trenton	15
Turku	15
Manchester	14
Tortona	14
Mazzano Romano	13
Salerno	13
Canale Monterano	12
Guidonia Montecelio	12
Changsha	11
Mol	11
Stockholm	11
Zhengzhou	11
Cham	10
Florence	10
Hanover	10
Johannesburg	10
Monza	10
Seattle	10
Tashkent	10
Brasília	9
Da Nang	9
Dresden	9
Hillsboro	9
London	9
Manheim	9
Mexico City	9
Rio de Janeiro	9
Chennai	8
Collecchio	8
Houston	8
Pisa	8
Redmond	8
Shenzhen	8
Totale	8.237

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Nome	#
Preliminary assessment of radiolysis for the cooling water system in the rotating target of SORGENTINA-RF	517
The current ALFRED core design	504
ALFRED reactor coolant system design	461
Overview on lead-cooled fast reactor design and related technologies development in ENEA	446
Core design for the UN-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR)	387
The core design of ALFRED, a demonstrator for the European lead-cooled reactors	352
CFD preliminary assessment of the ALFRED FA thermal-hydraulics	341
Westinghouse demonstration lead fast reactor in the context of the U.S. DOE advanced demonstration and test reactor options study	332
Core design for the UOX-fueled version of the Westinghouse Prototype Lead Fast Reactor (PLFR)	308
Core design for the UOX-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR)	307
ELSY Open Square Fuel Assembly Design and Drawings	293
Studi preliminari di tecniche di monitoraggio del nocciolo di ALFRED	291
Conseguenze del terremoto Tohoku-Taiheiyou-Oki sugli impianti nucleari giapponesi Ipotesi di ricostruzione della sequenza incidentale	286
ANTEO+: A subchannel code for thermal-hydraulic analysis of liquid metal cooled systems	284
Development of best estimate numerical tools for LFR design and safety analysis	278
Advanced fuel cost performance assessment for the westinghouse lfr	276
Procedure for pin-by-pin reconstruction of an ERANOS flux (power) in a Fuel Assembly	270
D6.1.1-3 – ALFRED core specifications	269
ALFRED Fuel Element Hexagonal Wrapper Conceptual Design	267
Characterization of the new ALFRED core configuration	267
Set up of a deterministic calculation model for the analysis of Fusion-Fission hybrid systems	264
Analisi neutronica per valutazioni di sicurezza del nocciolo di start-up di un PWR da 900 MWe	255
Nuclear data target accuracy requirements for advanced reactors: The ALFRED case	254
Extension of the “42-0” approach to ternary fuels and application to a thorium-fed, minor-actinides-burner ADS	253
Nuova concettualizzazione del nocciolo di DEMO-LFR: progetto preliminare neutronico, termoidraulico e termomeccanico	243
Nuclear Data Uncertainty Quantification and Propagation for Safety Analysis of Lead-Cooled Fast Reactors	240
Stress-testing the ALFRED design – Part I: Impact of nuclear data uncertainties on Design Extension Conditions transients	239
The physical principles of the ERANOS neutronic deterministic code and its application to the LFR and VENUS-F critical cores	237
Extension of the sub-channel code ANTEO+ to the mixed convection regime	236
LFR-120 Core neutronic verifications	234
Neutron propagation experiments with a lead test section inserted in the core of the LR-0 reactor	230
Caratterizzazione neutronica e termo/idraulica del nocciolo di AFRODITE	227
A Refined Assessment of Nuclear Data Target Accuracy Requirements for ALFRED	220
The steady state neutronic modelling of the ALFRED core by the ERANOS deterministic code with an in-depth study on shutdown systems design bases and performances	218
Results of the validation campaign of neutronic codes and recommendations for the correct application to LFR systems	218
Stress-testing the ALFRED design - Part III: Safety margins evaluation	216
Stress-testing the ALFRED design - Part II: Quantification of uncertainties on the fuel assembly temperature field	214
Studio di fattibilità per lo sviluppo di un modello multi-fisica (neutronica, termoidraulica e termomeccanica) di dinamica spaziale di nocciolo: rapporto di analisi della codicistica esistente a supporto dello sviluppo di uno strumento di dinamica spaziale di nocciolo	213
Ottimizzazione del progetto di nocciolo di ALFRED	210
DLFR core design summary	208
Uncertainty quantificaition on feedback and safety paramerters of the lead-cooled fast reactor	206
Preliminary evaluation of core compaction phenomenon: Methodological approach	200
Utilizzo di Apollo-Cronos per calcoli di criticità e di ciclo	198
Procedure for the automatic post-processing of ERANOS results into a format ready for visualization with Paraview	194
On the viability of In-Vessel Storage in the new ALFRED configuration	194
Results of the validation campaign of neutronic codes and reccomandations for the correct application to LFR systems	190
Development and preliminary validation of TIFONE, a design-oriented code for the inter-wrapper flow and heat transfer in liquid-metal-cooled reactors	189
LEADER Work Package 2 Work Program	181
Neutronic analyses aimed at the evaluation of the 30 MWth core criticality and burnup	179
Vision Paper for the development of a simulation platform in support to core design activities	179
Improvement of ALFRED thermal hydraulics through experiments and numerical studies	178
LFR Point Design study	175
Reactivity coefficients: recommended procedure for their evaluation	175
Static/dynamic DEMO core characterization	174
Report for Demonstration of Lead Fast Reactor Point Design	173
Tridimensional analysis of local perturbations on the core reactivity and the thermal-hydraulics of the fuel elements	170
Proposal for ALFRED core design	167
Revision of the DEMO core configuration and of its dynamic behaviour	167
Prevention and Mitigation of severe accidents through LFR core design – a case study: ELFR and ALFRED	162
Procedure for the computation of the main kinetic parameters with ERANOS and JEFF3.1	159
Lead Fast Reactor Thermal-Hydraulic Testing Facilities in Support of the UK Advanced Modular Reactor Program	65
Engagement Activities with the United Kingdom Regulators for the Westinghouse Lead Fast Reactor	54
Implementation of a Novel ERANOS Procedure for the Adjoint Power Evaluation in Coupled Depletion Problems	42
A neutronic model to find promising candidates as burnable poisons in fast reactors	34
Totale	15.170

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Categoria	#
all - tutte	56.847
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	56.847

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2021/2022	597	0	0	0	49	118	17	26	172	81	23	53	58
2022/2023	1.459	118	266	114	194	81	195	33	109	203	43	41	62
2023/2024	923	56	34	108	48	106	140	24	85	72	68	79	103
2024/2025	5.058	45	170	54	98	296	126	245	320	335	212	1.271	1.886
2025/2026	5.265	600	929	851	480	357	322	627	299	193	281	226	100
2026/2027	1.027	118	201	341	367	0	0	0	0	0	0	0	0
Totale													15.170