PORTO @ Archivio Istituzionale della Ricerca

ABRATE, NICOLO'
 Distribuzione geografica
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Continente #
EU - Europa 1.588
NA - Nord America 969
AS - Asia 416
AF - Africa 46
SA - Sud America 6
Continente sconosciuto - Info sul continente non disponibili 1
Totale 3.026
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Nazione #
IT - Italia 958
US - Stati Uniti d'America 954
SG - Singapore 173
BE - Belgio 129
CN - Cina 106
DE - Germania 106
FR - Francia 65
IE - Irlanda 58
RU - Federazione Russa 55
GB - Regno Unito 53
CH - Svizzera 35
CI - Costa d'Avorio 30
SE - Svezia 30
ID - Indonesia 28
KR - Corea 26
HK - Hong Kong 25
FI - Finlandia 24
TR - Turchia 23
ES - Italia 16
NL - Olanda 16
CA - Canada 15
SN - Senegal 14
NO - Norvegia 11
CZ - Repubblica Ceca 10
IQ - Iraq 8
IN - India 6
AT - Austria 5
JP - Giappone 5
SI - Slovenia 5
UA - Ucraina 5
BR - Brasile 4
JO - Giordania 4
MY - Malesia 4
BD - Bangladesh 3
BG - Bulgaria 3
RO - Romania 3
CO - Colombia 2
IL - Israele 2
A2 - ???statistics.table.value.countryCode.A2??? 1
IR - Iran 1
KE - Kenya 1
MA - Marocco 1
PH - Filippine 1
PT - Portogallo 1
SA - Arabia Saudita 1
Totale 3.026
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Città #
Turin 310
Singapore 142
Chandler 137
Brussels 117
Santa Clara 107
Torino 86
Milan 77
Boardman 63
Dublin 58
Ann Arbor 57
Ashburn 56
Princeton 52
Council Bluffs 41
Southend 32
Abidjan 30
Berlin 28
Rome 25
New York 24
Jakarta 23
Piscataway 22
Beijing 21
Bottanuco 21
Bremen 18
Wilmington 18
Istanbul 16
Verzuolo 16
Cambridge 14
Genoa 13
Helsinki 13
Bern 11
Oslo 11
San Donato Milanese 11
Seoul 11
Rheinfelden 10
Houston 8
Ne 8
Paris 8
Yubileyny 8
Borgosesia 7
Brno 7
Falls Church 7
Redmond 7
Redwood City 7
Toronto 7
Washington 7
Amsterdam 6
Bologna 6
Gif-sur-yvette 6
Lappeenranta 6
Moncalieri 6
Moscow 6
Bari 5
Biella 5
Brescia 5
Deruta 5
Izmir 5
Ljubljana 5
Miami 5
Mosul 5
Padova 5
Palermo 5
Parma 5
Raleigh 5
San Bernardino 5
Taranto 5
Vienna 5
Woodbridge 5
Arenzano 4
Aubervilliers 4
Cadoneghe 4
Cagliari 4
Columbia 4
Guangzhou 4
Lausanne 4
Mozzo 4
Munich 4
Savona 4
Seattle 4
Viterbo 4
Yogyakarta 4
York 4
Atlanta 3
Barcelona 3
Besançon 3
Boydton 3
Busto Arsizio 3
Castel Volturno 3
Dhaka 3
Essen 3
Esslingen am Neckar 3
Florence 3
Frankfurt am Main 3
Fuzhou 3
Genova 3
Kyiv 3
Kyoto 3
Laure-Minervois 3
Livorno Ferraris 3
London 3
Madrid 3
Totale 2.001
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Nome #
Neutronic benchmark of the FRENETIC code for the multiphysics analysis of lead fast reactors 177
Methods for safety and stability analysis of nuclear systems 149
Neutronic Analysis of the Fusion Reactor ARC: Monte Carlo Simulations with the Serpent Code 147
Genetic algorithm-based optimisation of the few-group structure for lead fast reactor analysis 120
Non-intrusive Uncertainty Propagation in the ARC Fusion Reactor through the nemoFOAM Multi-physics Tool 109
Assessment of numerical methods for the evaluation of higher-order harmonics in diffusion theory 97
Eigenvalue Formulations for the PN Approximation to the Neutron Transport Equation 97
Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design (dataset) 95
Neutron multiplication and fissile material distribution in a nuclear reactor 92
Coupled modelling of the EBR-II SHRT-45R including photon heat deposition 92
NUCLEAR DATA UNCERTAINTY QUANTIFICATION IN MOLTEN SALT REACTORS WITH XGPT 89
A Nonintrusive Nuclear Data Uncertainty Propagation Study for the ARC Fusion Reactor Design 88
Assessment of numerical methods for the evaluation of higher-order harmonics in diffusion theory 87
STUDY OF THE EIGENVALUE SPECTRA OF THE NEUTRON TRANSPORT PROBLEM IN PN APPROXIMATION 85
Nuclear data uncertainty quantification in the ARC fusion reactor 82
An OpenFOAM solver for multiphysics modeling of fusion reactor design: The nemoFoam code 81
Generalized perturbation techniques for uncertainty quantification in lead-cooled fast reactors 81
A generalised eigenvalue formulation for core-design applications 76
Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design 72
null 72
CONVERGENCE LIMITS IN PERTURBATION THEORY 72
On some features of the eigenvalue problem for the PN approximation of the neutron transport equation 70
A non-intrusive reduced order model for light water reactor core stability analysis 70
Alternative Weighting Functions for Group Collapsing of Nuclear Data in Lead Fast Reactors Time-dependent Analyses 69
Monte Carlo modelling of the ARC Breeding Blanket with the Serpent code  69
Spectrum features of the eigenvalue formulations in neutron transport 69
Uncertainty quantification in FRENETIC calculations of ALFRED lead-cooled fast reactor 64
Modelling the PbLi flow including tritium transport and permeation with GETTHEM 64
A non-intrusive reduced order model for the characterisation of the spatial power distribution in large thermal reactors 58
Code-to-code SIMMER/FRENETIC comparison for the neutronic simulation of lead-cooled fast reactors 56
A non-intrusive reduced order model for the characterisation of the spatial power distribution in large thermal reactors (dataset) 55
Convergence acceleration aspects in the solution of the PN neutron transport eigenvalue problem 55
A novel approach combining bootstrapped non-intrusive reduced order models and unscented transform for the robust and efficient CFD analysis of accidental gas releases in congested plants 54
Code-to-code SIMMER/FRENETIC comparison for the multiphysics simulation of the ALFRED core 51
Formulation of the Density Eigenvalue Problemin Neutron Transport for Relevant Engineering Applications 51
Neutronic analysis of the fusion reactor ARC: Monte Carlo simulations with the Serpent code (dataset) 47
Code-to-code SIMMER/FRENETIC comparison for the neutronic simulation of lead-cooled fast reactors (dataset) 44
A non-intrusive reduced order model for neutronic transient analyses of the ALFRED reactor 43
Generalized Perturbation Techniques for Uncertainty Quantification in Lead-Cooled Fast Reactors (dataset and software) 40
Spectrum features of the eigenvalue formulations in neutron transport (dataset) 31
Development of a New Thermal-Hydraulic Module for FRENETIC, a Code for the Multiphysics Analysis of Liquid Metal–Cooled Reactors 23
Development of a new Thermal-Hydraulic Module for FRENETIC, a Code for the Multiphysics Analysis of Liquid Metal-Cooled Reactors 15
Fissile distribution and the critical problem of a nuclear reactor: a mathematical approach 9
Totale 3.167
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Categoria #
all - tutte 11.249
article - articoli 4.961
book - libri 0
conference - conferenze 4.566
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 20.776
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/202096 0 0 0 0 0 29 3 9 19 17 8 11
2020/2021214 33 13 11 36 7 14 24 22 18 2 20 14
2021/2022367 33 4 11 23 27 16 15 18 24 32 91 73
2022/2023782 38 70 34 118 94 67 50 78 65 26 96 46
2023/2024835 24 58 33 94 57 115 78 48 81 42 73 132
2024/2025815 60 184 104 258 124 85 0 0 0 0 0 0
Totale 3.167