statistiche ricercatore

GRASSO, GIACOMO

Distribuzione geografica

Continente	#
EU - Europa	5.728
NA - Nord America	3.771
AS - Asia	2.200
SA - Sud America	361
AF - Africa	82
Continente sconosciuto - Info sul continente non disponibili	9
OC - Oceania	9
Totale	12.160

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Nazione	#
US - Stati Uniti d'America	3.556
RU - Federazione Russa	3.006
IT - Italia	1.121
SG - Singapore	988
CN - Cina	641
DE - Germania	436
BR - Brasile	322
GB - Regno Unito	304
SE - Svezia	263
HK - Hong Kong	197
CA - Canada	184
FR - Francia	153
FI - Finlandia	97
JP - Giappone	90
NL - Olanda	73
KR - Corea	70
AT - Austria	69
BE - Belgio	67
VN - Vietnam	59
MA - Marocco	51
IN - India	37
PL - Polonia	30
BD - Bangladesh	25
CH - Svizzera	23
MX - Messico	21
ES - Italia	17
UA - Ucraina	16
AR - Argentina	15
TR - Turchia	13
ZA - Sudafrica	13
RO - Romania	10
EU - Europa	9
IQ - Iraq	9
TW - Taiwan	9
IL - Israele	8
LT - Lituania	8
UZ - Uzbekistan	8
ID - Indonesia	7
TN - Tunisia	7
CZ - Repubblica Ceca	6
JO - Giordania	6
PE - Perù	6
TH - Thailandia	5
VE - Venezuela	5
AU - Australia	4
DK - Danimarca	4
EC - Ecuador	4
HU - Ungheria	4
KZ - Kazakistan	4
NZ - Nuova Zelanda	4
OM - Oman	4
AE - Emirati Arabi Uniti	3
BY - Bielorussia	3
CO - Colombia	3
EG - Egitto	3
GR - Grecia	3
IE - Irlanda	3
KE - Kenya	3
PH - Filippine	3
PS - Palestinian Territory	3
PT - Portogallo	3
AL - Albania	2
CL - Cile	2
DO - Repubblica Dominicana	2
HR - Croazia	2
IR - Iran	2
NI - Nicaragua	2
PA - Panama	2
PK - Pakistan	2
PY - Paraguay	2
SK - Slovacchia (Repubblica Slovacca)	2
AO - Angola	1
BH - Bahrain	1
BN - Brunei Darussalam	1
BO - Bolivia	1
CI - Costa d'Avorio	1
CY - Cipro	1
DM - Dominica	1
GT - Guatemala	1
JM - Giamaica	1
LB - Libano	1
LU - Lussemburgo	1
ML - Mali	1
MY - Malesia	1
NG - Nigeria	1
RS - Serbia	1
SA - Arabia Saudita	1
SI - Slovenia	1
SV - El Salvador	1
TL - Timor Orientale	1
TV - Tuvalu	1
UY - Uruguay	1
YT - Mayotte	1
Totale	12.160

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Città	#
Dallas	1.067
Moscow	688
Chandler	624
Singapore	502
Ashburn	232
Hefei	186
Santa Clara	182
Rome	181
Hong Kong	164
Toronto	158
Southend	148
San Mateo	147
Boardman	134
Munich	128
Hamburg	117
Beijing	107
New York	96
Milan	95
Helsinki	77
Turin	68
Bologna	62
Seoul	61
Council Bluffs	57
Berlin	56
The Dalles	52
Vienna	49
Redwood City	47
Casablanca	44
Los Angeles	44
Falkenstein	36
Brussels	35
Dong Ket	29
Washington	29
São Paulo	28
Jülich	27
Ann Arbor	26
Miami	26
Columbus	24
Marseille	21
Tokyo	21
Genoa	20
Las Vegas	19
Mountain View	18
Nuremberg	18
Paris	18
Warsaw	18
Belo Horizonte	17
Atlanta	16
Guangzhou	16
Dhaka	15
Trenton	15
Turku	15
Amsterdam	14
Phoenix	14
San Jose	14
Shanghai	14
Tortona	14
Brooklyn	13
Chicago	13
Mazzano Romano	13
Montreal	13
Salerno	13
Canale Monterano	12
Denver	12
Changsha	11
Mol	11
Zhengzhou	11
Cham	10
Frankfurt am Main	10
Hanover	10
Ho Chi Minh City	10
Orem	9
Collecchio	8
Johannesburg	8
Naples	8
Redmond	8
Rio de Janeiro	8
Stockholm	8
Tashkent	8
Boston	7
Cincinnati	7
Düsseldorf	7
Mexico City	7
Monza	7
Pisa	7
Piteå	7
Shenzhen	7
Wilmington	7
Brasília	6
Buffalo	6
Dubna	6
Hanoi	6
Heusden-Zolder	6
Inden	6
Langnau	6
Lucca	6
Lyon	6
Manchester	6
Padova	6
Seattle	6
Totale	6.512

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Nome	#
Preliminary assessment of radiolysis for the cooling water system in the rotating target of SORGENTINA-RF	425
ALFRED reactor coolant system design	385
The current ALFRED core design	374
Overview on lead-cooled fast reactor design and related technologies development in ENEA	369
Core design for the UN-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR)	327
CFD preliminary assessment of the ALFRED FA thermal-hydraulics	298
Westinghouse demonstration lead fast reactor in the context of the U.S. DOE advanced demonstration and test reactor options study	261
Core design for the UOX-fueled version of the Westinghouse Prototype Lead Fast Reactor (PLFR)	259
Core design for the UOX-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR)	249
The core design of ALFRED, a demonstrator for the European lead-cooled reactors	245
Advanced fuel cost performance assessment for the westinghouse lfr	237
Conseguenze del terremoto Tohoku-Taiheiyou-Oki sugli impianti nucleari giapponesi Ipotesi di ricostruzione della sequenza incidentale	237
Development of best estimate numerical tools for LFR design and safety analysis	237
ANTEO+: A subchannel code for thermal-hydraulic analysis of liquid metal cooled systems	233
ELSY Open Square Fuel Assembly Design and Drawings	232
Characterization of the new ALFRED core configuration	231
Procedure for pin-by-pin reconstruction of an ERANOS flux (power) in a Fuel Assembly	229
ALFRED Fuel Element Hexagonal Wrapper Conceptual Design	225
Set up of a deterministic calculation model for the analysis of Fusion-Fission hybrid systems	224
D6.1.1-3 – ALFRED core specifications	211
Analisi neutronica per valutazioni di sicurezza del nocciolo di start-up di un PWR da 900 MWe	209
Nuova concettualizzazione del nocciolo di DEMO-LFR: progetto preliminare neutronico, termoidraulico e termomeccanico	202
Extension of the sub-channel code ANTEO+ to the mixed convection regime	201
The physical principles of the ERANOS neutronic deterministic code and its application to the LFR and VENUS-F critical cores	199
Stress-testing the ALFRED design – Part I: Impact of nuclear data uncertainties on Design Extension Conditions transients	198
Nuclear data target accuracy requirements for advanced reactors: The ALFRED case	197
LFR-120 Core neutronic verifications	193
Studi preliminari di tecniche di monitoraggio del nocciolo di ALFRED	190
Nuclear Data Uncertainty Quantification and Propagation for Safety Analysis of Lead-Cooled Fast Reactors	190
Neutron propagation experiments with a lead test section inserted in the core of the LR-0 reactor	188
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	188
Caratterizzazione neutronica e termo/idraulica del nocciolo di AFRODITE	188
Stress-testing the ALFRED design - Part III: Safety margins evaluation	185
Ottimizzazione del progetto di nocciolo di ALFRED	184
Results of the validation campaign of neutronic codes and recommendations for the correct application to LFR systems	183
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	177
DLFR core design summary	175
Stress-testing the ALFRED design - Part II: Quantification of uncertainties on the fuel assembly temperature field	173
Preliminary evaluation of core compaction phenomenon: Methodological approach	170
Extension of the “42-0” approach to ternary fuels and application to a thorium-fed, minor-actinides-burner ADS	169
Uncertainty quantificaition on feedback and safety paramerters of the lead-cooled fast reactor	168
On the viability of In-Vessel Storage in the new ALFRED configuration	166
Procedure for the automatic post-processing of ERANOS results into a format ready for visualization with Paraview	165
Utilizzo di Apollo-Cronos per calcoli di criticità e di ciclo	164
A Refined Assessment of Nuclear Data Target Accuracy Requirements for ALFRED	164
Neutronic analyses aimed at the evaluation of the 30 MWth core criticality and burnup	158
Vision Paper for the development of a simulation platform in support to core design activities	155
LFR Point Design study	150
LEADER Work Package 2 Work Program	149
Reactivity coefficients: recommended procedure for their evaluation	146
Static/dynamic DEMO core characterization	143
Report for Demonstration of Lead Fast Reactor Point Design	142
Improvement of ALFRED thermal hydraulics through experiments and numerical studies	141
Tridimensional analysis of local perturbations on the core reactivity and the thermal-hydraulics of the fuel elements	141
Development and preliminary validation of TIFONE, a design-oriented code for the inter-wrapper flow and heat transfer in liquid-metal-cooled reactors	139
Results of the validation campaign of neutronic codes and reccomandations for the correct application to LFR systems	139
Proposal for ALFRED core design	137
Revision of the DEMO core configuration and of its dynamic behaviour	134
Prevention and Mitigation of severe accidents through LFR core design – a case study: ELFR and ALFRED	132
Procedure for the computation of the main kinetic parameters with ERANOS and JEFF3.1	128
Lead Fast Reactor Thermal-Hydraulic Testing Facilities in Support of the UK Advanced Modular Reactor Program	22
Implementation of a Novel ERANOS Procedure for the Adjoint Power Evaluation in Coupled Depletion Problems	4
Engagement Activities with the United Kingdom Regulators for the Westinghouse Lead Fast Reactor	1
Totale	12.235

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Categoria	#
all - tutte	47.651
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	47.651

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2020/2021	362	0	0	0	0	0	16	7	72	37	22	156	52
2021/2022	787	16	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	3.357	600	929	851	480	357	140	0	0	0	0	0	0
Totale													12.235