PORTO @ Archivio Istituzionale della Ricerca

ABRATE, NICOLO'
 Distribuzione geografica
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Continente #
AS - Asia 3.400
EU - Europa 3.211
NA - Nord America 3.090
SA - Sud America 310
AF - Africa 84
OC - Oceania 3
Continente sconosciuto - Info sul continente non disponibili 2
Totale 10.100
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Nazione #
US - Stati Uniti d'America 3.002
IT - Italia 1.709
SG - Singapore 1.018
VN - Vietnam 946
CN - Cina 540
RU - Federazione Russa 436
BR - Brasile 234
KR - Corea 216
FR - Francia 195
DE - Germania 188
HK - Hong Kong 149
BE - Belgio 142
BD - Bangladesh 103
GB - Regno Unito 100
IN - India 81
JP - Giappone 72
ES - Italia 65
FI - Finlandia 62
CA - Canada 60
IE - Irlanda 60
NL - Olanda 50
TR - Turchia 44
SE - Svezia 42
CH - Svizzera 40
ID - Indonesia 38
PH - Filippine 33
TW - Taiwan 33
CI - Costa d'Avorio 30
IQ - Iraq 27
TH - Thailandia 24
AR - Argentina 23
AT - Austria 20
SN - Senegal 16
UA - Ucraina 16
CO - Colombia 14
MX - Messico 14
EC - Ecuador 13
CZ - Repubblica Ceca 12
PL - Polonia 12
ZA - Sudafrica 12
NO - Norvegia 11
PK - Pakistan 10
BG - Bulgaria 9
PT - Portogallo 9
SI - Slovenia 9
MY - Malesia 8
SA - Arabia Saudita 8
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
LT - Lituania 5
OM - Oman 5
PE - Perù 5
RO - Romania 5
CR - Costa Rica 4
KZ - Kazakistan 4
UZ - Uzbekistan 4
AE - Emirati Arabi Uniti 3
AU - Australia 3
BY - Bielorussia 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
JM - Giamaica 2
PA - Panama 2
RS - Serbia 2
TT - Trinidad e Tobago 2
A2 - ???statistics.table.value.countryCode.A2??? 1
AO - Angola 1
AW - Aruba 1
BA - Bosnia-Erzegovina 1
BN - Brunei Darussalam 1
BW - Botswana 1
GT - Guatemala 1
HN - Honduras 1
KG - Kirghizistan 1
KY - Cayman, isole 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 10.100
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Città #
Singapore 620
Turin 503
San Jose 355
Ashburn 324
Ho Chi Minh City 271
Milan 215
Hanoi 207
Seoul 151
Santa Clara 144
Dallas 141
Chandler 137
Council Bluffs 123
Brussels 122
Los Angeles 109
Rome 104
Beijing 102
Hong Kong 98
Boardman 90
Torino 86
New York 82
Dublin 60
Hefei 60
Ann Arbor 57
Princeton 52
Lauterbourg 47
Tokyo 46
Moscow 44
Da Nang 42
Haiphong 38
Southend 32
Abidjan 30
Berlin 28
Jakarta 28
The Dalles 28
Munich 27
Bologna 26
Buffalo 25
São Paulo 23
Figino 22
Bottanuco 21
Lappeenranta 21
Piscataway 21
Columbus 20
Montreal 20
Frankfurt am Main 19
Genoa 19
Istanbul 19
Wilmington 19
Barcelona 18
Bremen 18
Helsinki 18
Cambridge 17
Houston 17
Verzuolo 16
Can Tho 15
Nuremberg 15
Orem 15
Amsterdam 13
Biên Hòa 13
Madrid 13
Toronto 13
London 12
Paris 12
Phoenix 12
Vienna 12
Bern 11
Borgosesia 11
Oslo 11
San Donato Milanese 11
Seattle 11
Shanghai 11
Ankara 10
Atlanta 10
Baghdad 10
Bari 10
Belo Horizonte 10
Denver 10
Florence 10
Guangzhou 10
Palermo 10
Parma 10
Redondo Beach 10
Rheinfelden 10
Turku 10
Warsaw 10
Chicago 9
Erfurt 9
Ljubljana 9
New Taipei City 9
Nice 9
Stockholm 9
Tân Tiến 9
Valencia 9
Washington 9
Bangkok 8
Bình Phước 8
Cagliari 8
Cangzhou 8
Chennai 8
Frisco 8
Totale 5.462
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Nome #
A Genetic-Driven Optimization of the Energy Grid Structure for Nodal Full-Core Calculations in Lead-Cooled Fast Reactors 372
An OpenFOAM solver for multiphysics modeling of fusion reactor design: The nemoFoam code 362
Modelling the PbLi flow including tritium transport and permeation with GETTHEM 308
Non-intrusive Uncertainty Propagation in the ARC Fusion Reactor through the nemoFOAM Multi-physics Tool 306
Neutronic benchmark of the FRENETIC code for the multiphysics analysis of lead fast reactors 291
Neutronic Analysis of the Fusion Reactor ARC: Monte Carlo Simulations with the Serpent Code 284
Genetic algorithm-based optimisation of the few-group structure for lead fast reactor analysis 267
A Nonintrusive Nuclear Data Uncertainty Propagation Study for the ARC Fusion Reactor Design 267
Methods for safety and stability analysis of nuclear systems 265
Nuclear data uncertainty quantification in the ARC fusion reactor 258
Alternative Weighting Functions for Group Collapsing of Nuclear Data in Lead Fast Reactors Time-dependent Analyses 249
Development of a New Thermal-Hydraulic Module for FRENETIC, a Code for the Multiphysics Analysis of Liquid Metal–Cooled Reactors 231
Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design 228
Coupled modelling of the EBR-II SHRT-45R including photon heat deposition 228
Spectrum features of the eigenvalue formulations in neutron transport 223
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 211
A non-intrusive reduced order model for the characterisation of the spatial power distribution in large thermal reactors 207
Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design (dataset) 204
Generalized perturbation techniques for uncertainty quantification in lead-cooled fast reactors 200
On some features of the eigenvalue problem for the PN approximation of the neutron transport equation 194
Development of a new Thermal-Hydraulic Module for FRENETIC, a Code for the Multiphysics Analysis of Liquid Metal-Cooled Reactors 183
Code-to-code SIMMER/FRENETIC comparison for the multiphysics simulation of the ALFRED core 182
Convergence acceleration aspects in the solution of the PN neutron transport eigenvalue problem 180
A generalised eigenvalue formulation for core-design applications 178
NUCLEAR DATA UNCERTAINTY QUANTIFICATION IN MOLTEN SALT REACTORS WITH XGPT 177
Eigenvalue Formulations for the PN Approximation to the Neutron Transport Equation 175
A non-intrusive reduced order model for neutronic transient analyses of the ALFRED reactor 173
Monte Carlo modelling of the ARC Breeding Blanket with the Serpent code  170
STUDY OF THE EIGENVALUE SPECTRA OF THE NEUTRON TRANSPORT PROBLEM IN PN APPROXIMATION 170
High-precision eigenvalues of the neutron transport equation by the Carlvik method 168
A non-intrusive reduced order model for light water reactor core stability analysis 167
Assessment of numerical methods for the evaluation of higher-order harmonics in diffusion theory 166
Monte Carlo and Deterministic Implementations of the Zeta-Eigenvalue Equation for Efficient Criticality Searches 163
Neutron multiplication and fissile material distribution in a nuclear reactor 163
Impact of energy collapsing on the effective neutron lifetime 150
Early warning in Molten Salt Fast Reactors based on a data-driven method for the online incident detection and diagnosis 149
Development and validation of magneto-hydrodynamics turbulence models for the thermal-hydraulic design of fusion reactor liquid blankets 147
Code-to-code SIMMER/FRENETIC comparison for the neutronic simulation of lead-cooled fast reactors 147
A genetic algorithm to optimize the multi-group structure for the neutronic analyses of the ARC fusion reactor 146
A non-intrusive reduced order model for the characterisation of the spatial power distribution in large thermal reactors (dataset) 143
Assessment of numerical methods for the evaluation of higher-order harmonics in diffusion theory 143
Formulation of the Density Eigenvalue Problemin Neutron Transport for Relevant Engineering Applications 141
Generalized Perturbation Techniques for Uncertainty Quantification in Lead-Cooled Fast Reactors (dataset and software) 140
Neutronic analysis of the fusion reactor ARC: Monte Carlo simulations with the Serpent code (dataset) 136
Uncertainty quantification in FRENETIC calculations of ALFRED lead-cooled fast reactor 135
Code-to-code SIMMER/FRENETIC comparison for the neutronic simulation of lead-cooled fast reactors (dataset) 131
Fissile distribution and the critical problem of a nuclear reactor: a mathematical approach 129
CONVERGENCE LIMITS IN PERTURBATION THEORY 121
Spectrum features of the eigenvalue formulations in neutron transport (dataset) 119
The Neutronics Codes FENNECS and FRENETIC: Code-to-code Benchmarking on Lead and Sodium-cooled Fast Reactors 118
Designing energy discretisations for sensitivity studies in lead-cooled fast reactors using a genetic algorithm 110
Cross Sections Generation and SPH Correction Methods for Deterministic Code Simulation of the Westinghouse LFR Design 109
A Monte Carlo Implementation of the ζ-Eigenvalue Equation 93
A genetic-driven optimisation of the energy grid structure for nodal full-core calculations in LFR (dataset) 69
A weight window approach for dose rate calculations in Lead-cooled Fast Reactors with OpenMC 69
Impact of energy collapsing on the effective neutron lifetime (dataset) 65
A Correction Ratio Approach to Fission Matrix Interpolation in Systems with Large Temperature Differences 7
Multi-Configuration Optimization of the Multi-group Energy Structure for Lead Fast Reactor simulations 6
A multi-group analytical model for the kinetic parameters 6
Group Constants Generation and SPH Correction Applied to the Westinghouse LFR design 5
Totale 10.304
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Categoria #
all - tutte 26.273
article - articoli 12.179
book - libri 0
conference - conferenze 10.355
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 48.807
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
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
2025/20265.982 346 198 378 465 492 370 726 530 1.126 608 245 498
2026/202768 68 0 0 0 0 0 0 0 0 0 0 0
Totale 10.304