statistiche ricercatore

GRASSO, GIACOMO

Distribuzione geografica

Continente	#
EU - Europa	6.036
NA - Nord America	4.502
AS - Asia	2.594
SA - Sud America	405
AF - Africa	99
OC - Oceania	11
Continente sconosciuto - Info sul continente non disponibili	9
Totale	13.656

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Nazione	#
US - Stati Uniti d'America	4.267
RU - Federazione Russa	3.008
IT - Italia	1.242
SG - Singapore	1.130
CN - Cina	704
DE - Germania	460
BR - Brasile	343
GB - Regno Unito	326
SE - Svezia	267
FR - Francia	242
HK - Hong Kong	206
CA - Canada	198
VN - Vietnam	168
FI - Finlandia	99
JP - Giappone	94
NL - Olanda	88
KR - Corea	74
AT - Austria	69
BE - Belgio	67
IN - India	56
MA - Marocco	52
PL - Polonia	33
BD - Bangladesh	29
MX - Messico	26
CH - Svizzera	25
ES - Italia	23
AR - Argentina	20
UA - Ucraina	19
TR - Turchia	18
ZA - Sudafrica	16
IQ - Iraq	15
RO - Romania	13
ID - Indonesia	11
UZ - Uzbekistan	10
EU - Europa	9
LT - Lituania	9
TN - Tunisia	9
TW - Taiwan	9
EC - Ecuador	8
IL - Israele	8
JO - Giordania	8
VE - Venezuela	8
CL - Cile	7
PK - Pakistan	7
AU - Australia	6
CZ - Repubblica Ceca	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
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
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
NI - Nicaragua	2
PA - Panama	2
SK - Slovacchia (Repubblica Slovacca)	2
AM - Armenia	1
BF - Burkina Faso	1
BH - Bahrain	1
BN - Brunei Darussalam	1
DM - Dominica	1
GH - Ghana	1
GT - Guatemala	1
JM - Giamaica	1
LB - Libano	1
LU - Lussemburgo	1
ML - Mali	1
MN - Mongolia	1
NG - Nigeria	1
NP - Nepal	1
RS - Serbia	1
SI - Slovenia	1
SN - Senegal	1
SV - El Salvador	1
TL - Timor Orientale	1
Totale	13.652

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Città	#
Dallas	1.072
Moscow	688
Chandler	624
Singapore	542
San Jose	450
Ashburn	334
Rome	193
Hefei	186
Santa Clara	184
Hong Kong	173
Toronto	162
Southend	148
San Mateo	147
Boardman	134
Munich	128
Hamburg	117
Beijing	107
Milan	104
New York	101
The Dalles	93
Helsinki	79
Turin	78
Bologna	68
Council Bluffs	64
Seoul	61
Berlin	57
Lauterbourg	57
Ho Chi Minh City	51
Los Angeles	51
Vienna	49
Redwood City	47
Casablanca	45
Paris	37
Falkenstein	36
Brussels	35
Hanoi	35
São Paulo	32
Washington	31
Dong Ket	29
Jülich	27
Ann Arbor	26
Miami	26
Orem	25
Tokyo	25
Columbus	24
Genoa	23
Marseille	23
Warsaw	21
Amsterdam	20
Atlanta	20
Montreal	20
Las Vegas	19
Belo Horizonte	18
Mountain View	18
Nuremberg	18
Chicago	17
Frankfurt am Main	17
Guangzhou	17
Phoenix	16
Denver	15
Dhaka	15
Naples	15
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
Buffalo	9
Dresden	9
Hillsboro	9
London	9
Mexico City	9
Rio de Janeiro	9
Chennai	8
Collecchio	8
Da Nang	8
Pisa	8
Redmond	8
Seattle	8
Amman	7
Boston	7
Brasília	7
Cincinnati	7
Düsseldorf	7
Monza	7
Piteå	7
Shenzhen	7
Wilmington	7
Totale	7.468

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Nome	#
Preliminary assessment of radiolysis for the cooling water system in the rotating target of SORGENTINA-RF	459
The current ALFRED core design	419
ALFRED reactor coolant system design	419
Overview on lead-cooled fast reactor design and related technologies development in ENEA	408
Core design for the UN-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR)	354
CFD preliminary assessment of the ALFRED FA thermal-hydraulics	322
The core design of ALFRED, a demonstrator for the European lead-cooled reactors	305
Core design for the UOX-fueled version of the Westinghouse Prototype Lead Fast Reactor (PLFR)	288
Westinghouse demonstration lead fast reactor in the context of the U.S. DOE advanced demonstration and test reactor options study	287
Core design for the UOX-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR)	274
Conseguenze del terremoto Tohoku-Taiheiyou-Oki sugli impianti nucleari giapponesi Ipotesi di ricostruzione della sequenza incidentale	264
Development of best estimate numerical tools for LFR design and safety analysis	263
ELSY Open Square Fuel Assembly Design and Drawings	261
Advanced fuel cost performance assessment for the westinghouse lfr	259
ANTEO+: A subchannel code for thermal-hydraulic analysis of liquid metal cooled systems	254
Characterization of the new ALFRED core configuration	253
Procedure for pin-by-pin reconstruction of an ERANOS flux (power) in a Fuel Assembly	252
Set up of a deterministic calculation model for the analysis of Fusion-Fission hybrid systems	247
ALFRED Fuel Element Hexagonal Wrapper Conceptual Design	246
Analisi neutronica per valutazioni di sicurezza del nocciolo di start-up di un PWR da 900 MWe	237
D6.1.1-3 – ALFRED core specifications	233
Nuova concettualizzazione del nocciolo di DEMO-LFR: progetto preliminare neutronico, termoidraulico e termomeccanico	233
Extension of the sub-channel code ANTEO+ to the mixed convection regime	225
Nuclear Data Uncertainty Quantification and Propagation for Safety Analysis of Lead-Cooled Fast Reactors	224
The physical principles of the ERANOS neutronic deterministic code and its application to the LFR and VENUS-F critical cores	222
Nuclear data target accuracy requirements for advanced reactors: The ALFRED case	220
Stress-testing the ALFRED design – Part I: Impact of nuclear data uncertainties on Design Extension Conditions transients	218
Studi preliminari di tecniche di monitoraggio del nocciolo di ALFRED	213
LFR-120 Core neutronic verifications	211
Caratterizzazione neutronica e termo/idraulica del nocciolo di AFRODITE	211
Neutron propagation experiments with a lead test section inserted in the core of the LR-0 reactor	206
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	206
Ottimizzazione del progetto di nocciolo di ALFRED	205
Stress-testing the ALFRED design - Part III: Safety margins evaluation	203
Results of the validation campaign of neutronic codes and recommendations for the correct application to LFR systems	203
Stress-testing the ALFRED design - Part II: Quantification of uncertainties on the fuel assembly temperature field	200
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	198
A Refined Assessment of Nuclear Data Target Accuracy Requirements for ALFRED	197
DLFR core design summary	196
Extension of the “42-0” approach to ternary fuels and application to a thorium-fed, minor-actinides-burner ADS	192
Preliminary evaluation of core compaction phenomenon: Methodological approach	189
Utilizzo di Apollo-Cronos per calcoli di criticità e di ciclo	189
Uncertainty quantificaition on feedback and safety paramerters of the lead-cooled fast reactor	187
On the viability of In-Vessel Storage in the new ALFRED configuration	182
Procedure for the automatic post-processing of ERANOS results into a format ready for visualization with Paraview	178
Neutronic analyses aimed at the evaluation of the 30 MWth core criticality and burnup	172
LEADER Work Package 2 Work Program	170
Development and preliminary validation of TIFONE, a design-oriented code for the inter-wrapper flow and heat transfer in liquid-metal-cooled reactors	169
Results of the validation campaign of neutronic codes and reccomandations for the correct application to LFR systems	169
Vision Paper for the development of a simulation platform in support to core design activities	169
LFR Point Design study	167
Improvement of ALFRED thermal hydraulics through experiments and numerical studies	164
Reactivity coefficients: recommended procedure for their evaluation	162
Report for Demonstration of Lead Fast Reactor Point Design	160
Static/dynamic DEMO core characterization	158
Tridimensional analysis of local perturbations on the core reactivity and the thermal-hydraulics of the fuel elements	156
Revision of the DEMO core configuration and of its dynamic behaviour	154
Proposal for ALFRED core design	153
Prevention and Mitigation of severe accidents through LFR core design – a case study: ELFR and ALFRED	150
Procedure for the computation of the main kinetic parameters with ERANOS and JEFF3.1	148
Lead Fast Reactor Thermal-Hydraulic Testing Facilities in Support of the UK Advanced Modular Reactor Program	40
Engagement Activities with the United Kingdom Regulators for the Westinghouse Lead Fast Reactor	34
Implementation of a Novel ERANOS Procedure for the Adjoint Power Evaluation in Coupled Depletion Problems	26
A neutronic model to find promising candidates as burnable poisons in fast reactors	6
Totale	13.739

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Categoria	#
all - tutte	50.363
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	50.363

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2020/2021	230	0	0	0	0	0	0	0	0	0	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	4.861	600	929	851	480	357	322	627	299	193	203	0	0
Totale													13.739