PORTO @ Archivio Istituzionale della Ricerca

ABRATE, NICOLO'
 Distribuzione geografica
Salva come PNG Salva come JPEG
Continente #
AS - Asia 3.451
EU - Europa 3.329
NA - Nord America 3.299
SA - Sud America 320
Continente sconosciuto - Info sul continente non disponibili 217
AF - Africa 84
OC - Oceania 3
Totale 10.703
Salva come PNG Salva come JPEG
Nazione #
US - Stati Uniti d'America 3.179
IT - Italia 1.800
SG - Singapore 1.036
VN - Vietnam 947
CN - Cina 545
RU - Federazione Russa 436
BR - Brasile 239
KR - Corea 218
FR - Francia 196
DE - Germania 189
HK - Hong Kong 149
BE - Belgio 143
BD - Bangladesh 118
GB - Regno Unito 105
IN - India 81
JP - Giappone 78
ES - Italia 74
CA - Canada 68
FI - Finlandia 62
IE - Irlanda 60
NL - Olanda 52
SE - Svezia 48
TR - Turchia 45
CH - Svizzera 41
ID - Indonesia 38
PH - Filippine 35
TW - Taiwan 33
CI - Costa d'Avorio 30
IQ - Iraq 27
AR - Argentina 24
TH - Thailandia 24
AT - Austria 20
SN - Senegal 16
UA - Ucraina 16
CO - Colombia 15
MX - Messico 15
EC - Ecuador 14
CZ - Repubblica Ceca 12
PL - Polonia 12
ZA - Sudafrica 12
NO - Norvegia 11
PK - Pakistan 10
SI - Slovenia 10
BG - Bulgaria 9
CR - Costa Rica 9
PT - Portogallo 9
JM - Giamaica 8
MY - Malesia 8
SA - Arabia Saudita 8
CL - Cile 7
PY - Paraguay 7
VE - Venezuela 7
KE - Kenya 6
MA - Marocco 6
AZ - Azerbaigian 5
EG - Egitto 5
IL - Israele 5
JO - Giordania 5
LT - Lituania 5
OM - Oman 5
PE - Perù 5
RO - Romania 5
TT - Trinidad e Tobago 5
HN - Honduras 4
KZ - Kazakistan 4
UZ - Uzbekistan 4
AE - Emirati Arabi Uniti 3
AU - Australia 3
BY - Bielorussia 3
DZ - Algeria 3
GE - Georgia 3
GT - Guatemala 3
IR - Iran 3
NP - Nepal 3
SY - Repubblica araba siriana 3
TN - Tunisia 3
AL - Albania 2
AM - Armenia 2
DK - Danimarca 2
HR - Croazia 2
HU - Ungheria 2
NI - Nicaragua 2
PA - Panama 2
RS - Serbia 2
UY - Uruguay 2
A2 - ???statistics.table.value.countryCode.A2??? 1
AO - Angola 1
AW - Aruba 1
BA - Bosnia-Erzegovina 1
BB - Barbados 1
BN - Brunei Darussalam 1
BW - Botswana 1
KG - Kirghizistan 1
KY - Cayman, isole 1
LA - Repubblica Popolare Democratica del Laos 1
MM - Myanmar 1
NG - Nigeria 1
QA - Qatar 1
SV - El Salvador 1
TJ - Tagikistan 1
Totale 10.487
Salva come PNG Salva come JPEG
Città #
Singapore 623
Turin 520
San Jose 365
Ashburn 341
Ho Chi Minh City 271
Milan 228
Hanoi 208
Council Bluffs 161
Santa Clara 153
Seoul 152
Dallas 145
Chandler 137
Brussels 122
Rome 114
Los Angeles 111
Beijing 105
Hong Kong 98
Boardman 90
Torino 86
New York 83
Dublin 60
Hefei 60
Ann Arbor 57
Princeton 52
Tokyo 48
Lauterbourg 47
Moscow 44
Da Nang 42
Haiphong 38
The Dalles 34
Southend 32
Abidjan 30
Berlin 28
Bologna 28
Jakarta 28
Buffalo 27
Munich 27
Barcelona 23
São Paulo 23
Figino 22
Bottanuco 21
Lappeenranta 21
Montreal 21
Piscataway 21
Columbus 20
Frankfurt am Main 20
Istanbul 20
Genoa 19
Phoenix 19
Wilmington 19
Bremen 18
Helsinki 18
Cambridge 17
Houston 17
Toronto 16
Verzuolo 16
Belo Horizonte 15
Can Tho 15
Nuremberg 15
Orem 15
Madrid 14
Stockholm 14
Amsterdam 13
Biên Hòa 13
London 12
Paris 12
Vienna 12
Atlanta 11
Bern 11
Borgosesia 11
Naples 11
Oslo 11
San Donato Milanese 11
Seattle 11
Shanghai 11
Ankara 10
Baghdad 10
Bari 10
Chicago 10
Denver 10
Florence 10
Guangzhou 10
Ljubljana 10
Palermo 10
Parma 10
Perugia 10
Redondo Beach 10
Rheinfelden 10
Turku 10
Warsaw 10
Washington 10
Cagliari 9
Erfurt 9
New Taipei City 9
Nice 9
San Francisco 9
Tân Tiến 9
Valencia 9
Bangkok 8
Brooklyn 8
Totale 5.643
Salva come PNG Salva come JPEG
Nome #
A Genetic-Driven Optimization of the Energy Grid Structure for Nodal Full-Core Calculations in Lead-Cooled Fast Reactors 399
An OpenFOAM solver for multiphysics modeling of fusion reactor design: The nemoFoam code 365
Modelling the PbLi flow including tritium transport and permeation with GETTHEM 315
Non-intrusive Uncertainty Propagation in the ARC Fusion Reactor through the nemoFOAM Multi-physics Tool 312
Neutronic benchmark of the FRENETIC code for the multiphysics analysis of lead fast reactors 294
Genetic algorithm-based optimisation of the few-group structure for lead fast reactor analysis 288
Neutronic Analysis of the Fusion Reactor ARC: Monte Carlo Simulations with the Serpent Code 288
Methods for safety and stability analysis of nuclear systems 272
Alternative Weighting Functions for Group Collapsing of Nuclear Data in Lead Fast Reactors Time-dependent Analyses 271
A Nonintrusive Nuclear Data Uncertainty Propagation Study for the ARC Fusion Reactor Design 271
Nuclear data uncertainty quantification in the ARC fusion reactor 263
Development of a New Thermal-Hydraulic Module for FRENETIC, a Code for the Multiphysics Analysis of Liquid Metal–Cooled Reactors 236
Coupled modelling of the EBR-II SHRT-45R including photon heat deposition 231
Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design 229
Spectrum features of the eigenvalue formulations in neutron transport 225
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 213
A non-intrusive reduced order model for the characterisation of the spatial power distribution in large thermal reactors 211
Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design (dataset) 208
Generalized perturbation techniques for uncertainty quantification in lead-cooled fast reactors 203
On some features of the eigenvalue problem for the PN approximation of the neutron transport equation 197
Code-to-code SIMMER/FRENETIC comparison for the multiphysics simulation of the ALFRED core 192
Development of a new Thermal-Hydraulic Module for FRENETIC, a Code for the Multiphysics Analysis of Liquid Metal-Cooled Reactors 187
Monte Carlo modelling of the ARC Breeding Blanket with the Serpent code  184
Convergence acceleration aspects in the solution of the PN neutron transport eigenvalue problem 182
A generalised eigenvalue formulation for core-design applications 180
NUCLEAR DATA UNCERTAINTY QUANTIFICATION IN MOLTEN SALT REACTORS WITH XGPT 180
Eigenvalue Formulations for the PN Approximation to the Neutron Transport Equation 179
STUDY OF THE EIGENVALUE SPECTRA OF THE NEUTRON TRANSPORT PROBLEM IN PN APPROXIMATION 175
A non-intrusive reduced order model for neutronic transient analyses of the ALFRED reactor 174
Monte Carlo and Deterministic Implementations of the Zeta-Eigenvalue Equation for Efficient Criticality Searches 172
A non-intrusive reduced order model for light water reactor core stability analysis 171
High-precision eigenvalues of the neutron transport equation by the Carlvik method 170
Assessment of numerical methods for the evaluation of higher-order harmonics in diffusion theory 168
Development and validation of magneto-hydrodynamics turbulence models for the thermal-hydraulic design of fusion reactor liquid blankets 165
Neutron multiplication and fissile material distribution in a nuclear reactor 165
Early warning in Molten Salt Fast Reactors based on a data-driven method for the online incident detection and diagnosis 161
Impact of energy collapsing on the effective neutron lifetime 156
A genetic algorithm to optimize the multi-group structure for the neutronic analyses of the ARC fusion reactor 152
Code-to-code SIMMER/FRENETIC comparison for the neutronic simulation of lead-cooled fast reactors 151
Assessment of numerical methods for the evaluation of higher-order harmonics in diffusion theory 145
A non-intrusive reduced order model for the characterisation of the spatial power distribution in large thermal reactors (dataset) 144
Formulation of the Density Eigenvalue Problemin Neutron Transport for Relevant Engineering Applications 144
Generalized Perturbation Techniques for Uncertainty Quantification in Lead-Cooled Fast Reactors (dataset and software) 142
Neutronic analysis of the fusion reactor ARC: Monte Carlo simulations with the Serpent code (dataset) 141
Code-to-code SIMMER/FRENETIC comparison for the neutronic simulation of lead-cooled fast reactors (dataset) 138
Uncertainty quantification in FRENETIC calculations of ALFRED lead-cooled fast reactor 136
The Neutronics Codes FENNECS and FRENETIC: Code-to-code Benchmarking on Lead and Sodium-cooled Fast Reactors 133
Fissile distribution and the critical problem of a nuclear reactor: a mathematical approach 131
CONVERGENCE LIMITS IN PERTURBATION THEORY 124
Spectrum features of the eigenvalue formulations in neutron transport (dataset) 121
Cross Sections Generation and SPH Correction Methods for Deterministic Code Simulation of the Westinghouse LFR Design 119
Designing energy discretisations for sensitivity studies in lead-cooled fast reactors using a genetic algorithm 116
A Monte Carlo Implementation of the ζ-Eigenvalue Equation 109
A weight window approach for dose rate calculations in Lead-cooled Fast Reactors with OpenMC 74
A genetic-driven optimisation of the energy grid structure for nodal full-core calculations in LFR (dataset) 72
Impact of energy collapsing on the effective neutron lifetime (dataset) 69
A multi-group analytical model for the kinetic parameters 20
Development of CRONO: A System Code for Safety-Informed Design of Liquid Metal-Cooled Fast Reactors 19
Group Constants Generation and SPH Correction Applied to the Westinghouse LFR design 19
Multi-Configuration Optimization of the Multi-group Energy Structure for Lead Fast Reactor simulations 17
A Correction Ratio Approach to Fission Matrix Interpolation in Systems with Large Temperature Differences 15
Totale 10.703
Salva come PNG Salva come JPEG
Categoria #
all - tutte 28.317
article - articoli 13.017
book - libri 0
conference - conferenze 11.338
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 52.672
Salva come PNG Salva come JPEG


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2021/2022330 0 0 11 23 27 16 15 18 24 32 91 73
2022/2023782 38 70 34 118 94 67 50 78 65 26 96 46
2023/2024830 24 58 33 94 57 111 78 48 81 42 73 131
2024/20251.907 60 182 104 258 122 105 133 141 272 121 194 215
2025/20265.982 346 198 378 465 492 370 726 530 1.126 608 245 498
2026/2027467 228 168 71 0 0 0 0 0 0 0 0 0
Totale 10.703