statistiche ricercatore

GRASSO, GIACOMO

Distribuzione geografica

Continente	#
EU - Europa	6.256
NA - Nord America	4.896
AS - Asia	2.633
SA - Sud America	409
AF - Africa	99
Continente sconosciuto - Info sul continente non disponibili	92
OC - Oceania	11
Totale	14.396

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Nazione	#
US - Stati Uniti d'America	4.651
RU - Federazione Russa	3.008
IT - Italia	1.387
SG - Singapore	1.132
CN - Cina	708
DE - Germania	460
BR - Brasile	346
GB - Regno Unito	328
SE - Svezia	305
FR - Francia	248
HK - Hong Kong	206
CA - Canada	202
VN - Vietnam	168
NL - Olanda	100
FI - Finlandia	99
JP - Giappone	96
KR - Corea	74
AT - Austria	69
BE - Belgio	67
BD - Bangladesh	59
IN - India	57
MA - Marocco	52
PL - Polonia	34
ES - Italia	32
CH - Svizzera	29
MX - Messico	26
AR - Argentina	20
UA - Ucraina	19
TR - Turchia	18
ZA - Sudafrica	16
IQ - Iraq	15
RO - Romania	14
ID - Indonesia	11
UZ - Uzbekistan	10
EC - Ecuador	9
EU - Europa	9
LT - Lituania	9
TN - Tunisia	9
TW - Taiwan	9
IL - Israele	8
JO - Giordania	8
VE - Venezuela	8
CL - Cile	7
CZ - Repubblica Ceca	7
PK - Pakistan	7
AU - Australia	6
IE - Irlanda	6
PE - Perù	6
PH - Filippine	6
CO - Colombia	5
HU - Ungheria	5
MY - Malesia	5
OM - Oman	5
PY - Paraguay	5
TH - Thailandia	5
AL - Albania	4
DK - Danimarca	4
EG - Egitto	4
GR - Grecia	4
HR - Croazia	4
KZ - Kazakistan	4
NI - Nicaragua	4
NZ - Nuova Zelanda	4
AE - Emirati Arabi Uniti	3
AO - Angola	3
BY - Bielorussia	3
KE - Kenya	3
PS - Palestinian Territory	3
PT - Portogallo	3
SA - Arabia Saudita	3
TT - Trinidad e Tobago	3
BG - Bulgaria	2
BO - Bolivia	2
CI - Costa d'Avorio	2
CY - Cipro	2
DO - Repubblica Dominicana	2
ET - Etiopia	2
IR - Iran	2
KG - Kirghizistan	2
LY - Libia	2
PA - Panama	2
SK - Slovacchia (Repubblica Slovacca)	2
AM - Armenia	1
BB - Barbados	1
BF - Burkina Faso	1
BH - Bahrain	1
BN - Brunei Darussalam	1
CR - Costa Rica	1
DM - Dominica	1
GH - Ghana	1
GT - Guatemala	1
JM - Giamaica	1
LB - Libano	1
LU - Lussemburgo	1
MK - Macedonia	1
ML - Mali	1
MN - Mongolia	1
NG - Nigeria	1
NP - Nepal	1
RS - Serbia	1
Totale	14.306

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Città	#
Dallas	1.078
Moscow	688
Chandler	624
Singapore	542
San Jose	521
Ashburn	360
Rome	218
Santa Clara	193
Hefei	186
Council Bluffs	183
Hong Kong	173
Toronto	163
Southend	148
San Mateo	147
Boardman	134
Munich	128
New York	124
Hamburg	117
Milan	114
Beijing	109
The Dalles	93
Turin	90
Helsinki	79
Bologna	77
Seoul	61
Los Angeles	60
Berlin	57
Lauterbourg	57
Ho Chi Minh City	51
Vienna	49
Redwood City	47
Casablanca	45
Paris	42
Falkenstein	36
Brussels	35
Hanoi	35
São Paulo	33
Washington	31
Dong Ket	29
Jülich	27
Ann Arbor	26
Miami	26
Tokyo	26
Genoa	25
Orem	25
Columbus	24
Marseille	23
Atlanta	22
Buffalo	22
Naples	22
Montreal	21
Phoenix	21
Warsaw	21
Amsterdam	20
Chicago	20
Las Vegas	19
Belo Horizonte	18
Mountain View	18
Nuremberg	18
Frankfurt am Main	17
Guangzhou	17
Denver	16
Dhaka	16
Shanghai	15
Trenton	15
Turku	15
Brooklyn	14
Manchester	14
Tortona	14
Mazzano Romano	13
Salerno	13
Canale Monterano	12
Changsha	11
Mol	11
Stockholm	11
Zhengzhou	11
Cham	10
Hanover	10
Johannesburg	10
Tashkent	10
Dresden	9
Hillsboro	9
London	9
Mexico City	9
Rio de Janeiro	9
Seattle	9
Chennai	8
Collecchio	8
Da Nang	8
Florence	8
Houston	8
Pisa	8
Redmond	8
Amman	7
Boston	7
Brasília	7
Cincinnati	7
Düsseldorf	7
Monza	7
Piteå	7
Totale	7.835

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Nome	#
Preliminary assessment of radiolysis for the cooling water system in the rotating target of SORGENTINA-RF	499
The current ALFRED core design	455
ALFRED reactor coolant system design	442
Overview on lead-cooled fast reactor design and related technologies development in ENEA	427
Core design for the UN-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR)	369
CFD preliminary assessment of the ALFRED FA thermal-hydraulics	329
The core design of ALFRED, a demonstrator for the European lead-cooled reactors	325
Westinghouse demonstration lead fast reactor in the context of the U.S. DOE advanced demonstration and test reactor options study	298
Core design for the UOX-fueled version of the Westinghouse Prototype Lead Fast Reactor (PLFR)	294
Core design for the UOX-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR)	283
Conseguenze del terremoto Tohoku-Taiheiyou-Oki sugli impianti nucleari giapponesi Ipotesi di ricostruzione della sequenza incidentale	279
ANTEO+: A subchannel code for thermal-hydraulic analysis of liquid metal cooled systems	270
ELSY Open Square Fuel Assembly Design and Drawings	270
Advanced fuel cost performance assessment for the westinghouse lfr	268
Development of best estimate numerical tools for LFR design and safety analysis	266
Procedure for pin-by-pin reconstruction of an ERANOS flux (power) in a Fuel Assembly	261
Characterization of the new ALFRED core configuration	258
ALFRED Fuel Element Hexagonal Wrapper Conceptual Design	257
Studi preliminari di tecniche di monitoraggio del nocciolo di ALFRED	252
D6.1.1-3 – ALFRED core specifications	251
Set up of a deterministic calculation model for the analysis of Fusion-Fission hybrid systems	249
Analisi neutronica per valutazioni di sicurezza del nocciolo di start-up di un PWR da 900 MWe	248
Extension of the “42-0” approach to ternary fuels and application to a thorium-fed, minor-actinides-burner ADS	244
Nuclear data target accuracy requirements for advanced reactors: The ALFRED case	241
Nuova concettualizzazione del nocciolo di DEMO-LFR: progetto preliminare neutronico, termoidraulico e termomeccanico	236
Nuclear Data Uncertainty Quantification and Propagation for Safety Analysis of Lead-Cooled Fast Reactors	233
Extension of the sub-channel code ANTEO+ to the mixed convection regime	229
The physical principles of the ERANOS neutronic deterministic code and its application to the LFR and VENUS-F critical cores	228
Stress-testing the ALFRED design – Part I: Impact of nuclear data uncertainties on Design Extension Conditions transients	225
LFR-120 Core neutronic verifications	223
Caratterizzazione neutronica e termo/idraulica del nocciolo di AFRODITE	219
Neutron propagation experiments with a lead test section inserted in the core of the LR-0 reactor	216
Stress-testing the ALFRED design - Part III: Safety margins evaluation	211
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	211
Results of the validation campaign of neutronic codes and recommendations for the correct application to LFR systems	209
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	207
Stress-testing the ALFRED design - Part II: Quantification of uncertainties on the fuel assembly temperature field	207
A Refined Assessment of Nuclear Data Target Accuracy Requirements for ALFRED	207
Ottimizzazione del progetto di nocciolo di ALFRED	206
DLFR core design summary	202
Preliminary evaluation of core compaction phenomenon: Methodological approach	191
Utilizzo di Apollo-Cronos per calcoli di criticità e di ciclo	191
Uncertainty quantificaition on feedback and safety paramerters of the lead-cooled fast reactor	191
Procedure for the automatic post-processing of ERANOS results into a format ready for visualization with Paraview	188
On the viability of In-Vessel Storage in the new ALFRED configuration	186
Results of the validation campaign of neutronic codes and reccomandations for the correct application to LFR systems	182
Development and preliminary validation of TIFONE, a design-oriented code for the inter-wrapper flow and heat transfer in liquid-metal-cooled reactors	181
Neutronic analyses aimed at the evaluation of the 30 MWth core criticality and burnup	173
LEADER Work Package 2 Work Program	172
Vision Paper for the development of a simulation platform in support to core design activities	172
Reactivity coefficients: recommended procedure for their evaluation	169
Improvement of ALFRED thermal hydraulics through experiments and numerical studies	168
LFR Point Design study	168
Report for Demonstration of Lead Fast Reactor Point Design	165
Tridimensional analysis of local perturbations on the core reactivity and the thermal-hydraulics of the fuel elements	164
Proposal for ALFRED core design	161
Static/dynamic DEMO core characterization	161
Revision of the DEMO core configuration and of its dynamic behaviour	158
Prevention and Mitigation of severe accidents through LFR core design – a case study: ELFR and ALFRED	156
Procedure for the computation of the main kinetic parameters with ERANOS and JEFF3.1	152
Lead Fast Reactor Thermal-Hydraulic Testing Facilities in Support of the UK Advanced Modular Reactor Program	51
Engagement Activities with the United Kingdom Regulators for the Westinghouse Lead Fast Reactor	41
Implementation of a Novel ERANOS Procedure for the Adjoint Power Evaluation in Coupled Depletion Problems	31
A neutronic model to find promising candidates as burnable poisons in fast reactors	20
Totale	14.396

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Categoria	#
all - tutte	54.426
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	54.426

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2021/2022	771	0	157	17	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	253	118	135	0	0	0	0	0	0	0	0	0	0
Totale													14.396