PORTO @ Archivio Istituzionale della Ricerca

ABRATE, NICOLO'
 Distribuzione geografica
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Continente #
AS - Asia 3.292
EU - Europa 2.863
NA - Nord America 2.800
SA - Sud America 309
AF - Africa 83
OC - Oceania 3
Continente sconosciuto - Info sul continente non disponibili 2
Totale 9.352
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Nazione #
US - Stati Uniti d'America 2.733
IT - Italia 1.388
SG - Singapore 1.003
VN - Vietnam 946
CN - Cina 536
RU - Federazione Russa 436
BR - Brasile 234
KR - Corea 213
FR - Francia 188
DE - Germania 186
HK - Hong Kong 147
BE - Belgio 140
GB - Regno Unito 98
IN - India 81
JP - Giappone 72
ES - Italia 61
FI - Finlandia 61
IE - Irlanda 60
NL - Olanda 48
CA - Canada 46
TR - Turchia 41
CH - Svizzera 40
SE - Svezia 40
ID - Indonesia 37
PH - Filippine 33
TW - Taiwan 33
CI - Costa d'Avorio 30
IQ - Iraq 27
TH - Thailandia 24
AR - Argentina 23
BD - Bangladesh 23
AT - Austria 20
SN - Senegal 16
UA - Ucraina 15
CO - Colombia 13
EC - Ecuador 13
MX - Messico 13
CZ - Repubblica Ceca 12
NO - Norvegia 11
PL - Polonia 11
ZA - Sudafrica 11
PK - Pakistan 10
PT - Portogallo 9
SI - Slovenia 9
MY - Malesia 8
SA - Arabia Saudita 8
BG - Bulgaria 7
CL - Cile 7
PY - Paraguay 7
KE - Kenya 6
MA - Marocco 6
VE - Venezuela 6
AZ - Azerbaigian 5
EG - Egitto 5
IL - Israele 5
JO - Giordania 5
OM - Oman 5
PE - Perù 5
RO - Romania 5
KZ - Kazakistan 4
LT - Lituania 4
UZ - Uzbekistan 4
AE - Emirati Arabi Uniti 3
AU - Australia 3
BY - Bielorussia 3
CR - Costa Rica 3
DZ - Algeria 3
GE - Georgia 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
IR - Iran 2
PA - Panama 2
RS - Serbia 2
TT - Trinidad e Tobago 2
A2 - ???statistics.table.value.countryCode.A2??? 1
AO - Angola 1
BA - Bosnia-Erzegovina 1
BN - Brunei Darussalam 1
BW - Botswana 1
JM - Giamaica 1
KG - Kirghizistan 1
LA - Repubblica Popolare Democratica del Laos 1
MM - Myanmar 1
NG - Nigeria 1
QA - Qatar 1
TJ - Tagikistan 1
UY - Uruguay 1
XK - ???statistics.table.value.countryCode.XK??? 1
Totale 9.352
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Città #
Singapore 619
Turin 482
Ashburn 304
San Jose 297
Ho Chi Minh City 271
Hanoi 207
Seoul 151
Dallas 139
Chandler 137
Santa Clara 136
Brussels 120
Milan 119
Beijing 101
Los Angeles 100
Hong Kong 97
Torino 86
Council Bluffs 82
New York 68
Boardman 63
Dublin 60
Hefei 60
Ann Arbor 57
Princeton 52
Lauterbourg 47
Rome 46
Tokyo 46
Moscow 44
Da Nang 42
Haiphong 38
Southend 32
Abidjan 30
Berlin 28
Jakarta 28
The Dalles 28
Munich 27
São Paulo 23
Buffalo 22
Bologna 21
Bottanuco 21
Lappeenranta 21
Piscataway 21
Columbus 20
Frankfurt am Main 19
Genoa 19
Istanbul 19
Montreal 19
Barcelona 18
Bremen 18
Helsinki 18
Wilmington 18
Cambridge 17
Houston 17
Verzuolo 16
Can Tho 15
Nuremberg 15
Orem 14
Amsterdam 13
Biên Hòa 13
Madrid 13
London 12
Paris 12
Phoenix 12
Toronto 12
Vienna 12
Bern 11
Borgosesia 11
Oslo 11
San Donato Milanese 11
Atlanta 10
Baghdad 10
Belo Horizonte 10
Denver 10
Guangzhou 10
Parma 10
Redondo Beach 10
Rheinfelden 10
Seattle 10
Shanghai 10
Turku 10
Warsaw 10
Ljubljana 9
New Taipei City 9
Stockholm 9
Tân Tiến 9
Bangkok 8
Bình Phước 8
Cangzhou 8
Chennai 8
Ne 8
Trento 8
Yubileyny 8
Ankara 7
Brno 7
Brooklyn 7
Chicago 7
Dhaka 7
Erfurt 7
Falls Church 7
Lisbon 7
Manchester 7
Totale 5.053
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Nome #
An OpenFOAM solver for multiphysics modeling of fusion reactor design: The nemoFoam code 329
A Genetic-Driven Optimization of the Energy Grid Structure for Nodal Full-Core Calculations in Lead-Cooled Fast Reactors 314
Non-intrusive Uncertainty Propagation in the ARC Fusion Reactor through the nemoFOAM Multi-physics Tool 294
Neutronic benchmark of the FRENETIC code for the multiphysics analysis of lead fast reactors 287
Neutronic Analysis of the Fusion Reactor ARC: Monte Carlo Simulations with the Serpent Code 281
Modelling the PbLi flow including tritium transport and permeation with GETTHEM 274
Methods for safety and stability analysis of nuclear systems 260
Genetic algorithm-based optimisation of the few-group structure for lead fast reactor analysis 259
A Nonintrusive Nuclear Data Uncertainty Propagation Study for the ARC Fusion Reactor Design 258
Nuclear data uncertainty quantification in the ARC fusion reactor 249
Alternative Weighting Functions for Group Collapsing of Nuclear Data in Lead Fast Reactors Time-dependent Analyses 234
Coupled modelling of the EBR-II SHRT-45R including photon heat deposition 221
Spectrum features of the eigenvalue formulations in neutron transport 219
Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design 213
Development of a New Thermal-Hydraulic Module for FRENETIC, a Code for the Multiphysics Analysis of Liquid Metal–Cooled Reactors 210
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 197
A non-intrusive reduced order model for the characterisation of the spatial power distribution in large thermal reactors 197
Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design (dataset) 193
On some features of the eigenvalue problem for the PN approximation of the neutron transport equation 190
Generalized perturbation techniques for uncertainty quantification in lead-cooled fast reactors 188
Convergence acceleration aspects in the solution of the PN neutron transport eigenvalue problem 176
A generalised eigenvalue formulation for core-design applications 176
Code-to-code SIMMER/FRENETIC comparison for the multiphysics simulation of the ALFRED core 172
Eigenvalue Formulations for the PN Approximation to the Neutron Transport Equation 172
Development of a new Thermal-Hydraulic Module for FRENETIC, a Code for the Multiphysics Analysis of Liquid Metal-Cooled Reactors 167
STUDY OF THE EIGENVALUE SPECTRA OF THE NEUTRON TRANSPORT PROBLEM IN PN APPROXIMATION 167
Assessment of numerical methods for the evaluation of higher-order harmonics in diffusion theory 163
Neutron multiplication and fissile material distribution in a nuclear reactor 157
A non-intrusive reduced order model for light water reactor core stability analysis 157
A non-intrusive reduced order model for neutronic transient analyses of the ALFRED reactor 155
NUCLEAR DATA UNCERTAINTY QUANTIFICATION IN MOLTEN SALT REACTORS WITH XGPT 154
Monte Carlo modelling of the ARC Breeding Blanket with the Serpent code  153
Code-to-code SIMMER/FRENETIC comparison for the neutronic simulation of lead-cooled fast reactors 143
A non-intrusive reduced order model for the characterisation of the spatial power distribution in large thermal reactors (dataset) 142
Impact of energy collapsing on the effective neutron lifetime 142
Assessment of numerical methods for the evaluation of higher-order harmonics in diffusion theory 141
Generalized Perturbation Techniques for Uncertainty Quantification in Lead-Cooled Fast Reactors (dataset and software) 138
Formulation of the Density Eigenvalue Problemin Neutron Transport for Relevant Engineering Applications 138
High-precision eigenvalues of the neutron transport equation by the Carlvik method 136
Neutronic analysis of the fusion reactor ARC: Monte Carlo simulations with the Serpent code (dataset) 132
Uncertainty quantification in FRENETIC calculations of ALFRED lead-cooled fast reactor 132
Code-to-code SIMMER/FRENETIC comparison for the neutronic simulation of lead-cooled fast reactors (dataset) 129
Monte Carlo and Deterministic Implementations of the Zeta-Eigenvalue Equation for Efficient Criticality Searches 127
Fissile distribution and the critical problem of a nuclear reactor: a mathematical approach 127
CONVERGENCE LIMITS IN PERTURBATION THEORY 120
A genetic algorithm to optimize the multi-group structure for the neutronic analyses of the ARC fusion reactor 118
Spectrum features of the eigenvalue formulations in neutron transport (dataset) 115
Development and validation of magneto-hydrodynamics turbulence models for the thermal-hydraulic design of fusion reactor liquid blankets 114
Early warning in Molten Salt Fast Reactors based on a data-driven method for the online incident detection and diagnosis 112
The Neutronics Codes FENNECS and FRENETIC: Code-to-code Benchmarking on Lead and Sodium-cooled Fast Reactors 88
Designing energy discretisations for sensitivity studies in lead-cooled fast reactors using a genetic algorithm 87
Cross Sections Generation and SPH Correction Methods for Deterministic Code Simulation of the Westinghouse LFR Design 82
A Monte Carlo Implementation of the ζ-Eigenvalue Equation 73
A weight window approach for dose rate calculations in Lead-cooled Fast Reactors with OpenMC 64
Impact of energy collapsing on the effective neutron lifetime (dataset) 56
A genetic-driven optimisation of the energy grid structure for nodal full-core calculations in LFR (dataset) 56
Totale 9.548
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Categoria #
all - tutte 23.986
article - articoli 11.098
book - libri 0
conference - conferenze 9.432
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 44.516
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/202134 0 0 0 0 0 0 0 0 0 0 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
2025/20265.294 346 198 378 465 492 370 726 530 1.126 608 55 0
Totale 9.548