FIORINA, CARLO
 Distribuzione geografica
Continente #
NA - Nord America 1.624
EU - Europa 395
AS - Asia 104
AF - Africa 13
SA - Sud America 4
OC - Oceania 1
Totale 2.141
Nazione #
US - Stati Uniti d'America 1.603
AT - Austria 90
IT - Italia 81
FI - Finlandia 40
UA - Ucraina 37
GB - Regno Unito 36
VN - Vietnam 36
DE - Germania 31
JO - Giordania 25
CN - Cina 24
SE - Svezia 24
CA - Canada 21
IE - Irlanda 19
EG - Egitto 12
BE - Belgio 10
KR - Corea 9
FR - Francia 8
NL - Olanda 6
IN - India 5
CL - Cile 4
RU - Federazione Russa 4
ES - Italia 3
CH - Svizzera 2
SG - Singapore 2
AU - Australia 1
CZ - Repubblica Ceca 1
DK - Danimarca 1
GR - Grecia 1
HU - Ungheria 1
IR - Iran 1
JP - Giappone 1
MU - Mauritius 1
TR - Turchia 1
Totale 2.141
Città #
Fairfield 240
Chandler 197
Woodbridge 164
Houston 142
Ann Arbor 113
Wilmington 100
Ashburn 90
Vienna 89
Cambridge 87
Seattle 85
Jacksonville 31
Amman 25
Lawrence 25
Medford 24
Milan 21
Dearborn 20
Dong Ket 20
Ottawa 20
Dublin 19
Des Moines 17
Helsinki 14
Beijing 13
Alexandria 11
Boardman 10
Brussels 10
San Diego 7
Auburn Hills 6
Falls Church 6
Redwood City 6
Washington 6
Mountain View 5
New York 4
Raleigh 4
Udine 4
Indiana 3
Legnano 3
Málaga 3
Paris 3
Seoul 3
Shanghai 3
Amsterdam 2
Chennai 2
Columbus 2
Gessate 2
London 2
Los Angeles 2
New Bedfont 2
Norwalk 2
Olgiate Olona 2
Pohang 2
Singapore 2
Tappahannock 2
Windisch 2
Athens 1
Atlanta 1
Cardiff 1
Casteldaccia 1
Chaoyang 1
Charlotte 1
Civitavecchia 1
Copenhagen 1
Csömör 1
Dallas 1
Delft 1
Dresden 1
Duncan 1
Espoo 1
Frosinone 1
Giza 1
Groningen 1
Gunzenhausen 1
Islington 1
Kish 1
Lake Forest 1
Lombard 1
Lonate Pozzolo 1
Mclean 1
Miami 1
Mianyang 1
Minneapolis 1
Montréal 1
Nanchang 1
Nanjing 1
Phoenix 1
Pittsburgh 1
Portland 1
Prague 1
Princeton 1
Redcar 1
Rodigo 1
San Ramon 1
St Louis 1
Tokyo 1
Treviglio 1
Uppsala 1
Yellow Springs 1
Zhengzhou 1
Totale 1.723
Nome #
An extended version of the SERPENT-2 code to investigate fuel burn-up and core material evolution of the Molten Salt Fast Reactor 140
Safety Analysis - Transient Calculations 126
Comparative analysis of thorium and uranium fuel for transuranic recycle in a sodium cooled Fast Reactor 124
Investigation of the MSFR core physics and fuel cycle characteristics 124
A multi-physics time-dependent model for the Lead Fast Reactor single-channel analysis 120
A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics 109
An Approach for the Modelling and the Analysis of the MSR Thermo-Hydrodynamic Behaviour 107
Analysis of thorium and uranium fuel cycles in an iso-breeder lead fast reactor using extended-EQL3D procedure 106
Dimensional Effects in the Modelling of MSR Dynamics: Moving on from Simplified Schemes of Analysis to a Multi-Physics Modelling Approach 105
Analysis of the MSFR Core Neutronics Adopting Different Neutron Transport Models 101
Modelling and analysis of the MSFR transient behaviour 99
Thermal-hydraulics of internally heated molten salts and application to the Molten Salt Fast Reactor 92
A preliminary study of the MSFR dynamics 91
Development of a Single-Channel Multi-Physics Model for Lead Fast Reactors 81
Preliminary Analysis of the MSFR Fuel Cycle Using Modified- EQL3D Procedure 79
MSFR TRU-BURNING POTENTIAL AND COMPARISON WITH AN SFR 72
A Multi-Physics Numerical Model for the MSR Core Dynamics 69
Thermal-hydraulics of internally heated molten salts and application to the Molten Salt Fast Reactor 69
Thermo-Hydrodynamics of Internally Heated Molten Salts for Innovative Nuclear Reactors 62
Preliminary Assessment of Modelling Issues Related to the Dynamics and Control of Graphite-Moderated MSRs 61
Analysis of Void Reactivity and Doppler Coefficient for Thorium- And Uranium-Fuelled Lead Fast Reactors 60
An Innovative Approach to Dynamics Modeling and Simulation of the Molten Salt Rector Experiment 44
Development of a Simulation Tool for a Preliminary Analysis of the MSR Core Dynamics 43
Thorium-based Fast Reactors: Potential Benefits and Challenges 42
THE MSFR AS A FLEXIBLE CR REACTOR: THE VIEWPOINT OF SAFETY 29
On the need for multi-dimensional models for the safety analysis of (fast-spectrum) Molten Salt Reactors 16
IAEA INITIATIVE ON OPEN-SOURCE NUCLEAR CODES FOR REACTOR ANALYSIS 5
Totale 2.176
Categoria #
all - tutte 5.854
article - articoli 3.042
book - libri 0
conference - conferenze 2.397
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 168
Totale 11.461


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2018/2019173 0 0 0 0 0 0 0 0 0 0 91 82
2019/2020501 40 24 9 49 63 59 58 47 58 32 45 17
2020/2021235 19 16 44 6 18 9 10 24 12 21 12 44
2021/2022195 2 39 9 3 10 19 12 12 9 6 19 55
2022/2023396 34 43 1 72 36 44 0 22 77 4 23 40
2023/2024142 18 30 34 5 5 5 23 11 3 8 0 0
Totale 2.176