PORTO @ Archivio Istituzionale della Ricerca

ABRATE, NICOLO'
 Distribuzione geografica
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Continente #
EU - Europa 2.207
NA - Nord America 1.920
AS - Asia 1.750
SA - Sud America 242
AF - Africa 62
Continente sconosciuto - Info sul continente non disponibili 1
OC - Oceania 1
Totale 6.183
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Nazione #
US - Stati Uniti d'America 1.875
IT - Italia 1.269
SG - Singapore 803
CN - Cina 486
BR - Brasile 197
DE - Germania 157
BE - Belgio 138
KR - Corea 138
FR - Francia 116
VN - Vietnam 87
GB - Regno Unito 83
RU - Federazione Russa 66
IE - Irlanda 59
ES - Italia 57
FI - Finlandia 53
NL - Olanda 41
SE - Svezia 38
CH - Svizzera 37
HK - Hong Kong 37
TR - Turchia 36
CA - Canada 35
ID - Indonesia 33
JP - Giappone 32
CI - Costa d'Avorio 30
IN - India 20
AT - Austria 18
AR - Argentina 16
IQ - Iraq 16
SN - Senegal 15
BD - Bangladesh 12
CZ - Repubblica Ceca 11
NO - Norvegia 11
PL - Polonia 11
UA - Ucraina 10
CO - Colombia 8
EC - Ecuador 8
MX - Messico 8
SI - Slovenia 8
MY - Malesia 7
BG - Bulgaria 6
PY - Paraguay 6
ZA - Sudafrica 6
AZ - Azerbaigian 5
IL - Israele 5
JO - Giordania 4
LT - Lituania 4
MA - Marocco 4
OM - Oman 4
PK - Pakistan 4
RO - Romania 4
SA - Arabia Saudita 4
KE - Kenya 3
PE - Perù 3
PT - Portogallo 3
AM - Armenia 2
BY - Bielorussia 2
CL - Cile 2
DK - Danimarca 2
DZ - Algeria 2
IR - Iran 2
KZ - Kazakistan 2
TW - Taiwan 2
UZ - Uzbekistan 2
VE - Venezuela 2
A2 - ???statistics.table.value.countryCode.A2??? 1
AL - Albania 1
AU - Australia 1
BN - Brunei Darussalam 1
EG - Egitto 1
GE - Georgia 1
HU - Ungheria 1
JM - Giamaica 1
KG - Kirghizistan 1
LA - Repubblica Popolare Democratica del Laos 1
NP - Nepal 1
PA - Panama 1
PH - Filippine 1
RS - Serbia 1
TJ - Tagikistan 1
TN - Tunisia 1
Totale 6.183
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Città #
Singapore 470
Turin 442
Ashburn 220
Chandler 137
Dallas 135
Santa Clara 124
Brussels 119
Milan 112
Beijing 97
Seoul 96
Torino 86
Boardman 62
Dublin 59
Council Bluffs 58
Ann Arbor 57
Hefei 53
Princeton 52
New York 46
Los Angeles 37
Rome 35
Southend 32
Ho Chi Minh City 31
Abidjan 30
Berlin 28
Munich 27
Jakarta 25
Tokyo 24
Hanoi 22
Bottanuco 21
Piscataway 21
Buffalo 19
Bremen 18
Istanbul 18
Lappeenranta 18
Wilmington 18
Cambridge 17
São Paulo 16
Verzuolo 16
Barcelona 15
Genoa 15
Houston 15
Bologna 14
Helsinki 14
Montreal 14
Nuremberg 14
Madrid 13
Hong Kong 12
Bern 11
Oslo 11
Phoenix 11
San Donato Milanese 11
The Dalles 11
Belo Horizonte 10
Redondo Beach 10
Rheinfelden 10
Shanghai 10
Turku 10
Vienna 10
Warsaw 10
Atlanta 9
Denver 9
Frankfurt am Main 9
Guangzhou 9
San Jose 9
Seattle 9
Amsterdam 8
Cangzhou 8
Ljubljana 8
Ne 8
Paris 8
Toronto 8
Trento 8
Yubileyny 8
Borgosesia 7
Brno 7
Columbus 7
Falls Church 7
London 7
Manchester 7
Moscow 7
Nantes 7
Redmond 7
Redwood City 7
Stockholm 7
Valencia 7
Washington 7
Boston 6
Brooklyn 6
Cadoneghe 6
Chicago 6
Daun 6
Gif-sur-yvette 6
Moncalieri 6
Mosul 6
Noisy-le-Grand 6
Poplar 6
Ankara 5
Baku 5
Bari 5
Biella 5
Totale 3.438
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Nome #
An OpenFOAM solver for multiphysics modeling of fusion reactor design: The nemoFoam code 261
Neutronic Analysis of the Fusion Reactor ARC: Monte Carlo Simulations with the Serpent Code 232
Neutronic benchmark of the FRENETIC code for the multiphysics analysis of lead fast reactors 231
Methods for safety and stability analysis of nuclear systems 227
Non-intrusive Uncertainty Propagation in the ARC Fusion Reactor through the nemoFOAM Multi-physics Tool 215
Nuclear data uncertainty quantification in the ARC fusion reactor 207
Genetic algorithm-based optimisation of the few-group structure for lead fast reactor analysis 182
A Nonintrusive Nuclear Data Uncertainty Propagation Study for the ARC Fusion Reactor Design 181
Modelling the PbLi flow including tritium transport and permeation with GETTHEM 174
Alternative Weighting Functions for Group Collapsing of Nuclear Data in Lead Fast Reactors Time-dependent Analyses 166
Coupled modelling of the EBR-II SHRT-45R including photon heat deposition 161
Spectrum features of the eigenvalue formulations in neutron transport 159
A Genetic-Driven Optimization of the Energy Grid Structure for Nodal Full-Core Calculations in Lead-Cooled Fast Reactors 151
Development of a New Thermal-Hydraulic Module for FRENETIC, a Code for the Multiphysics Analysis of Liquid Metal–Cooled Reactors 151
Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design 146
Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design (dataset) 145
A non-intrusive reduced order model for the characterisation of the spatial power distribution in large thermal reactors 144
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 142
Eigenvalue Formulations for the PN Approximation to the Neutron Transport Equation 141
Generalized perturbation techniques for uncertainty quantification in lead-cooled fast reactors 136
A generalised eigenvalue formulation for core-design applications 132
On some features of the eigenvalue problem for the PN approximation of the neutron transport equation 132
STUDY OF THE EIGENVALUE SPECTRA OF THE NEUTRON TRANSPORT PROBLEM IN PN APPROXIMATION 127
Assessment of numerical methods for the evaluation of higher-order harmonics in diffusion theory 124
A non-intrusive reduced order model for light water reactor core stability analysis 122
Neutron multiplication and fissile material distribution in a nuclear reactor 121
A non-intrusive reduced order model for the characterisation of the spatial power distribution in large thermal reactors (dataset) 120
Monte Carlo modelling of the ARC Breeding Blanket with the Serpent code  117
Code-to-code SIMMER/FRENETIC comparison for the multiphysics simulation of the ALFRED core 115
NUCLEAR DATA UNCERTAINTY QUANTIFICATION IN MOLTEN SALT REACTORS WITH XGPT 113
Development of a new Thermal-Hydraulic Module for FRENETIC, a Code for the Multiphysics Analysis of Liquid Metal-Cooled Reactors 111
A non-intrusive reduced order model for neutronic transient analyses of the ALFRED reactor 105
Assessment of numerical methods for the evaluation of higher-order harmonics in diffusion theory 105
Code-to-code SIMMER/FRENETIC comparison for the neutronic simulation of lead-cooled fast reactors 105
Generalized Perturbation Techniques for Uncertainty Quantification in Lead-Cooled Fast Reactors (dataset and software) 101
Convergence acceleration aspects in the solution of the PN neutron transport eigenvalue problem 99
Uncertainty quantification in FRENETIC calculations of ALFRED lead-cooled fast reactor 97
Neutronic analysis of the fusion reactor ARC: Monte Carlo simulations with the Serpent code (dataset) 94
Formulation of the Density Eigenvalue Problemin Neutron Transport for Relevant Engineering Applications 92
CONVERGENCE LIMITS IN PERTURBATION THEORY 89
Code-to-code SIMMER/FRENETIC comparison for the neutronic simulation of lead-cooled fast reactors (dataset) 87
Fissile distribution and the critical problem of a nuclear reactor: a mathematical approach 87
Impact of energy collapsing on the effective neutron lifetime 85
Spectrum features of the eigenvalue formulations in neutron transport (dataset) 78
The Neutronics Codes FENNECS and FRENETIC: Code-to-code Benchmarking on Lead and Sodium-cooled Fast Reactors 38
High-precision eigenvalues of the neutron transport equation by the Carlvik method 36
Development and validation of magneto-hydrodynamics turbulence models for the thermal-hydraulic design of fusion reactor liquid blankets 36
Cross Sections Generation and SPH Correction Methods for Deterministic Code Simulation of the Westinghouse LFR Design 28
A Monte Carlo Implementation of the ζ-Eigenvalue Equation 28
Designing energy discretisations for sensitivity studies in lead-cooled fast reactors using a genetic algorithm 24
Monte Carlo and Deterministic Implementations of the Zeta-Eigenvalue Equation for Efficient Criticality Searches 23
A weight window approach for dose rate calculations in Lead-cooled Fast Reactors with OpenMC 21
A genetic-driven optimisation of the energy grid structure for nodal full-core calculations in LFR (dataset) 17
Impact of energy collapsing on the effective neutron lifetime (dataset) 12
Early warning in Molten Salt Fast Reactors based on a data-driven method for the online incident detection and diagnosis 1
Totale 6.374
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Categoria #
all - tutte 19.397
article - articoli 8.879
book - libri 0
conference - conferenze 7.589
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 35.865
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021114 0 0 0 0 0 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
2023/2024830 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
2025/20262.120 346 198 378 465 492 241 0 0 0 0 0 0
Totale 6.374