GRASSO, GIACOMO
 Distribuzione geografica
Continente #
EU - Europa 5.503
NA - Nord America 2.314
AS - Asia 1.216
SA - Sud America 327
AF - Africa 29
Continente sconosciuto - Info sul continente non disponibili 9
OC - Oceania 8
Totale 9.406
Nazione #
RU - Federazione Russa 3.004
US - Stati Uniti d'America 2.137
IT - Italia 987
SG - Singapore 465
DE - Germania 426
CN - Cina 344
BR - Brasile 293
GB - Regno Unito 293
SE - Svezia 258
CA - Canada 158
HK - Hong Kong 154
FR - Francia 141
FI - Finlandia 97
JP - Giappone 81
AT - Austria 68
BE - Belgio 66
NL - Olanda 66
IN - India 34
VN - Vietnam 33
BD - Bangladesh 22
CH - Svizzera 20
PL - Polonia 17
UA - Ucraina 13
TR - Turchia 12
AR - Argentina 11
MX - Messico 10
ES - Italia 9
EU - Europa 9
KR - Corea 9
TW - Taiwan 8
UZ - Uzbekistan 8
IL - Israele 7
IQ - Iraq 7
MA - Marocco 7
TN - Tunisia 7
ZA - Sudafrica 7
PE - Perù 6
CZ - Repubblica Ceca 5
JO - Giordania 5
RO - Romania 5
VE - Venezuela 5
DK - Danimarca 4
EC - Ecuador 4
HU - Ungheria 4
KZ - Kazakistan 4
NZ - Nuova Zelanda 4
OM - Oman 4
AU - Australia 3
CO - Colombia 3
EG - Egitto 3
GR - Grecia 3
IE - Irlanda 3
PT - Portogallo 3
TH - Thailandia 3
AE - Emirati Arabi Uniti 2
AL - Albania 2
BY - Bielorussia 2
CL - Cile 2
DO - Repubblica Dominicana 2
HR - Croazia 2
ID - Indonesia 2
IR - Iran 2
KE - Kenya 2
NI - Nicaragua 2
PA - Panama 2
PK - Pakistan 2
PS - Palestinian Territory 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
GT - Guatemala 1
JM - Giamaica 1
LT - Lituania 1
NG - Nigeria 1
PH - Filippine 1
PY - Paraguay 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
Totale 9.406
Città #
Moscow 688
Chandler 624
Singapore 208
Santa Clara 170
Southend 148
Toronto 148
San Mateo 147
Boardman 134
Rome 131
Hong Kong 130
Ashburn 122
Munich 121
Hamburg 117
Milan 88
Beijing 85
Helsinki 77
New York 77
Turin 57
Berlin 56
Bologna 51
Vienna 49
Redwood City 47
The Dalles 39
Council Bluffs 38
Falkenstein 36
Brussels 35
Dong Ket 29
Washington 29
Jülich 27
Ann Arbor 26
Columbus 24
Los Angeles 24
Miami 24
Marseille 21
Genoa 20
Las Vegas 19
Mountain View 18
Nuremberg 18
Belo Horizonte 17
Dhaka 15
São Paulo 15
Trenton 15
Turku 15
Tortona 14
Mazzano Romano 13
Salerno 13
Shanghai 13
Tokyo 13
Amsterdam 12
Canale Monterano 12
Guangzhou 11
Phoenix 11
Brooklyn 10
Cham 10
Frankfurt am Main 10
Hanover 10
Mol 10
San Jose 10
Zhengzhou 10
Changsha 9
Paris 9
Atlanta 8
Chicago 8
Collecchio 8
Redmond 8
Tashkent 8
Cincinnati 7
Düsseldorf 7
Pisa 7
Piteå 7
Rio de Janeiro 7
Warsaw 7
Wilmington 7
Buffalo 6
Dubna 6
Heusden-Zolder 6
Inden 6
Langnau 6
Lucca 6
Lyon 6
Naples 6
Padova 6
Shenzhen 6
Boston 5
Brasília 5
Cava de' Tirreni 5
Chennai 5
Como 5
Curitiba 5
Falls Church 5
Florence 5
Guarulhos 5
Hefei 5
Lauterbourg 5
Marino 5
St Petersburg 5
Taichung 5
Xi'an 5
Albuquerque 4
Amman 4
Totale 4.411
Nome #
Preliminary assessment of radiolysis for the cooling water system in the rotating target of SORGENTINA-RF 333
The current ALFRED core design 314
Overview on lead-cooled fast reactor design and related technologies development in ENEA 291
ALFRED reactor coolant system design 274
Core design for the UN-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR) 253
Westinghouse demonstration lead fast reactor in the context of the U.S. DOE advanced demonstration and test reactor options study 222
The core design of ALFRED, a demonstrator for the European lead-cooled reactors 201
Set up of a deterministic calculation model for the analysis of Fusion-Fission hybrid systems 199
Advanced fuel cost performance assessment for the westinghouse lfr 192
Development of best estimate numerical tools for LFR design and safety analysis 189
CFD preliminary assessment of the ALFRED FA thermal-hydraulics 189
Conseguenze del terremoto Tohoku-Taiheiyou-Oki sugli impianti nucleari giapponesi Ipotesi di ricostruzione della sequenza incidentale 180
ELSY Open Square Fuel Assembly Design and Drawings 178
Core design for the UOX-fueled version of the Westinghouse Prototype Lead Fast Reactor (PLFR) 176
ANTEO+: A subchannel code for thermal-hydraulic analysis of liquid metal cooled systems 175
Core design for the UOX-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR) 175
Stress-testing the ALFRED design – Part I: Impact of nuclear data uncertainties on Design Extension Conditions transients 168
D6.1.1-3 – ALFRED core specifications 168
ALFRED Fuel Element Hexagonal Wrapper Conceptual Design 168
Nuova concettualizzazione del nocciolo di DEMO-LFR: progetto preliminare neutronico, termoidraulico e termomeccanico 168
Stress-testing the ALFRED design - Part III: Safety margins evaluation 164
Characterization of the new ALFRED core configuration 164
Procedure for pin-by-pin reconstruction of an ERANOS flux (power) in a Fuel Assembly 162
Studi preliminari di tecniche di monitoraggio del nocciolo di ALFRED 160
The physical principles of the ERANOS neutronic deterministic code and its application to the LFR and VENUS-F critical cores 159
Extension of the sub-channel code ANTEO+ to the mixed convection regime 157
Nuclear data target accuracy requirements for advanced reactors: The ALFRED case 157
Stress-testing the ALFRED design - Part II: Quantification of uncertainties on the fuel assembly temperature field 155
Ottimizzazione del progetto di nocciolo di ALFRED 155
LFR-120 Core neutronic verifications 153
Nuclear Data Uncertainty Quantification and Propagation for Safety Analysis of Lead-Cooled Fast Reactors 153
Neutron propagation experiments with a lead test section inserted in the core of the LR-0 reactor 150
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 147
Results of the validation campaign of neutronic codes and recommendations for the correct application to LFR systems 145
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 144
Preliminary evaluation of core compaction phenomenon: Methodological approach 143
Analisi neutronica per valutazioni di sicurezza del nocciolo di start-up di un PWR da 900 MWe 141
Caratterizzazione neutronica e termo/idraulica del nocciolo di AFRODITE 138
Uncertainty quantificaition on feedback and safety paramerters of the lead-cooled fast reactor 134
Procedure for the automatic post-processing of ERANOS results into a format ready for visualization with Paraview 132
On the viability of In-Vessel Storage in the new ALFRED configuration 130
Neutronic analyses aimed at the evaluation of the 30 MWth core criticality and burnup 129
Utilizzo di Apollo-Cronos per calcoli di criticità e di ciclo 129
DLFR core design summary 127
Vision Paper for the development of a simulation platform in support to core design activities 125
LEADER Work Package 2 Work Program 123
LFR Point Design study 121
Static/dynamic DEMO core characterization 117
Reactivity coefficients: recommended procedure for their evaluation 116
Report for Demonstration of Lead Fast Reactor Point Design 116
Tridimensional analysis of local perturbations on the core reactivity and the thermal-hydraulics of the fuel elements 115
Proposal for ALFRED core design 112
Prevention and Mitigation of severe accidents through LFR core design – a case study: ELFR and ALFRED 112
Results of the validation campaign of neutronic codes and reccomandations for the correct application to LFR systems 112
Procedure for the computation of the main kinetic parameters with ERANOS and JEFF3.1 108
Revision of the DEMO core configuration and of its dynamic behaviour 108
Extension of the “42-0” approach to ternary fuels and application to a thorium-fed, minor-actinides-burner ADS 98
Improvement of ALFRED thermal hydraulics through experiments and numerical studies 92
A Refined Assessment of Nuclear Data Target Accuracy Requirements for ALFRED 86
Development and preliminary validation of TIFONE, a design-oriented code for the inter-wrapper flow and heat transfer in liquid-metal-cooled reactors 76
Totale 9.478
Categoria #
all - tutte 41.737
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 41.737


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021553 0 31 22 26 112 16 7 72 37 22 156 52
2021/2022787 16 157 17 49 118 17 26 172 81 23 53 58
2022/20231.459 118 266 114 194 81 195 33 109 203 43 41 62
2023/2024923 56 34 108 48 106 140 24 85 72 68 79 103
2024/20255.058 45 170 54 98 296 126 245 320 335 212 1.271 1.886
2025/2026600 600 0 0 0 0 0 0 0 0 0 0 0
Totale 9.478