statistiche ricercatore

GRASSO, GIACOMO

Distribuzione geografica

Continente	#
EU - Europa	6.163
NA - Nord America	4.744
AS - Asia	2.619
SA - Sud America	406
AF - Africa	99
OC - Oceania	11
Continente sconosciuto - Info sul continente non disponibili	9
Totale	14.051

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Nazione	#
US - Stati Uniti d'America	4.505
RU - Federazione Russa	3.008
IT - Italia	1.336
SG - Singapore	1.132
CN - Cina	705
DE - Germania	460
BR - Brasile	344
GB - Regno Unito	327
SE - Svezia	288
FR - Francia	242
HK - Hong Kong	206
CA - Canada	201
VN - Vietnam	168
FI - Finlandia	99
JP - Giappone	95
NL - Olanda	94
KR - Corea	74
AT - Austria	69
BE - Belgio	67
IN - India	56
MA - Marocco	52
BD - Bangladesh	50
PL - Polonia	33
CH - Svizzera	29
MX - Messico	26
ES - Italia	23
AR - Argentina	20
UA - Ucraina	19
TR - Turchia	18
ZA - Sudafrica	16
IQ - Iraq	15
RO - Romania	14
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
CR - Costa Rica	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
Totale	14.046

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Città	#
Dallas	1.076
Moscow	688
Chandler	624
Singapore	542
San Jose	521
Ashburn	350
Rome	211
Santa Clara	191
Hefei	186
Hong Kong	173
Toronto	163
Southend	148
San Mateo	147
Boardman	134
Munich	128
New York	123
Council Bluffs	118
Hamburg	117
Milan	110
Beijing	108
The Dalles	93
Turin	89
Helsinki	79
Bologna	74
Seoul	61
Berlin	57
Lauterbourg	57
Los Angeles	57
Ho Chi Minh City	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
Genoa	25
Orem	25
Tokyo	25
Columbus	24
Marseille	23
Buffalo	21
Montreal	21
Naples	21
Warsaw	21
Amsterdam	20
Atlanta	20
Chicago	20
Las Vegas	19
Belo Horizonte	18
Mountain View	18
Nuremberg	18
Frankfurt am Main	17
Guangzhou	17
Phoenix	17
Denver	15
Dhaka	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
Dresden	9
Hillsboro	9
London	9
Mexico City	9
Rio de Janeiro	9
Seattle	9
Chennai	8
Collecchio	8
Da Nang	8
Pisa	8
Redmond	8
Amman	7
Boston	7
Brasília	7
Cincinnati	7
Düsseldorf	7
Florence	7
Houston	7
Monza	7
Piteå	7
Totale	7.717

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Nome	#
Preliminary assessment of radiolysis for the cooling water system in the rotating target of SORGENTINA-RF	490
The current ALFRED core design	439
ALFRED reactor coolant system design	435
Overview on lead-cooled fast reactor design and related technologies development in ENEA	419
Core design for the UN-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR)	364
CFD preliminary assessment of the ALFRED FA thermal-hydraulics	328
The core design of ALFRED, a demonstrator for the European lead-cooled reactors	314
Core design for the UOX-fueled version of the Westinghouse Prototype Lead Fast Reactor (PLFR)	293
Westinghouse demonstration lead fast reactor in the context of the U.S. DOE advanced demonstration and test reactor options study	290
Core design for the UOX-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR)	279
Conseguenze del terremoto Tohoku-Taiheiyou-Oki sugli impianti nucleari giapponesi Ipotesi di ricostruzione della sequenza incidentale	276
Advanced fuel cost performance assessment for the westinghouse lfr	266
ELSY Open Square Fuel Assembly Design and Drawings	265
ANTEO+: A subchannel code for thermal-hydraulic analysis of liquid metal cooled systems	264
Development of best estimate numerical tools for LFR design and safety analysis	264
Procedure for pin-by-pin reconstruction of an ERANOS flux (power) in a Fuel Assembly	260
Characterization of the new ALFRED core configuration	257
ALFRED Fuel Element Hexagonal Wrapper Conceptual Design	253
Set up of a deterministic calculation model for the analysis of Fusion-Fission hybrid systems	248
Studi preliminari di tecniche di monitoraggio del nocciolo di ALFRED	247
D6.1.1-3 – ALFRED core specifications	243
Analisi neutronica per valutazioni di sicurezza del nocciolo di start-up di un PWR da 900 MWe	243
Nuclear data target accuracy requirements for advanced reactors: The ALFRED case	237
Nuova concettualizzazione del nocciolo di DEMO-LFR: progetto preliminare neutronico, termoidraulico e termomeccanico	234
Nuclear Data Uncertainty Quantification and Propagation for Safety Analysis of Lead-Cooled Fast Reactors	228
Extension of the sub-channel code ANTEO+ to the mixed convection regime	226
The physical principles of the ERANOS neutronic deterministic code and its application to the LFR and VENUS-F critical cores	226
Stress-testing the ALFRED design – Part I: Impact of nuclear data uncertainties on Design Extension Conditions transients	221
LFR-120 Core neutronic verifications	221
Caratterizzazione neutronica e termo/idraulica del nocciolo di AFRODITE	216
Neutron propagation experiments with a lead test section inserted in the core of the LR-0 reactor	212
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	210
Stress-testing the ALFRED design - Part III: Safety margins evaluation	207
Results of the validation campaign of neutronic codes and recommendations for the correct application to LFR systems	207
Ottimizzazione del progetto di nocciolo di ALFRED	205
A Refined Assessment of Nuclear Data Target Accuracy Requirements for ALFRED	205
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	204
Stress-testing the ALFRED design - Part II: Quantification of uncertainties on the fuel assembly temperature field	202
DLFR core design summary	200
Extension of the “42-0” approach to ternary fuels and application to a thorium-fed, minor-actinides-burner ADS	198
Uncertainty quantificaition on feedback and safety paramerters of the lead-cooled fast reactor	190
Preliminary evaluation of core compaction phenomenon: Methodological approach	189
Utilizzo di Apollo-Cronos per calcoli di criticità e di ciclo	189
Procedure for the automatic post-processing of ERANOS results into a format ready for visualization with Paraview	186
On the viability of In-Vessel Storage in the new ALFRED configuration	185
Development and preliminary validation of TIFONE, a design-oriented code for the inter-wrapper flow and heat transfer in liquid-metal-cooled reactors	180
Results of the validation campaign of neutronic codes and reccomandations for the correct application to LFR systems	179
Neutronic analyses aimed at the evaluation of the 30 MWth core criticality and burnup	172
LEADER Work Package 2 Work Program	171
Vision Paper for the development of a simulation platform in support to core design activities	171
Improvement of ALFRED thermal hydraulics through experiments and numerical studies	167
LFR Point Design study	167
Reactivity coefficients: recommended procedure for their evaluation	167
Report for Demonstration of Lead Fast Reactor Point Design	164
Tridimensional analysis of local perturbations on the core reactivity and the thermal-hydraulics of the fuel elements	161
Static/dynamic DEMO core characterization	159
Proposal for ALFRED core design	158
Prevention and Mitigation of severe accidents through LFR core design – a case study: ELFR and ALFRED	155
Revision of the DEMO core configuration and of its dynamic behaviour	155
Procedure for the computation of the main kinetic parameters with ERANOS and JEFF3.1	150
Lead Fast Reactor Thermal-Hydraulic Testing Facilities in Support of the UK Advanced Modular Reactor Program	43
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	30
A neutronic model to find promising candidates as burnable poisons in fast reactors	16
Totale	14.134

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Categoria	#
all - tutte	52.697
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	52.697

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2020/2021	52	0	0	0	0	0	0	0	0	0	0	0	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	5.256	600	929	851	480	357	322	627	299	193	281	226	91
Totale													14.134