PORTO @ Archivio Istituzionale della Ricerca

ABRATE, NICOLO'
 Distribuzione geografica
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Continente #
EU - Europa 2.085
NA - Nord America 1.679
AS - Asia 1.410
SA - Sud America 211
AF - Africa 51
Continente sconosciuto - Info sul continente non disponibili 1
OC - Oceania 1
Totale 5.438
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Nazione #
US - Stati Uniti d'America 1.647
IT - Italia 1.219
SG - Singapore 621
CN - Cina 446
BR - Brasile 176
DE - Germania 147
BE - Belgio 133
KR - Corea 127
FR - Francia 110
GB - Regno Unito 68
RU - Federazione Russa 63
IE - Irlanda 59
ES - Italia 47
FI - Finlandia 47
NL - Olanda 40
CH - Svizzera 37
TR - Turchia 35
SE - Svezia 34
ID - Indonesia 32
CI - Costa d'Avorio 30
HK - Hong Kong 29
CA - Canada 25
VN - Vietnam 21
JP - Giappone 20
IN - India 16
AT - Austria 15
SN - Senegal 14
IQ - Iraq 13
AR - Argentina 11
NO - Norvegia 11
CZ - Repubblica Ceca 10
BD - Bangladesh 9
UA - Ucraina 9
SI - Slovenia 8
CO - Colombia 7
EC - Ecuador 7
PL - Polonia 7
BG - Bulgaria 6
MY - Malesia 6
IL - Israele 5
MX - Messico 5
PY - Paraguay 5
JO - Giordania 4
RO - Romania 4
SA - Arabia Saudita 4
AZ - Azerbaigian 3
LT - Lituania 3
PT - Portogallo 3
AM - Armenia 2
BY - Bielorussia 2
IR - Iran 2
KE - Kenya 2
OM - Oman 2
PE - Perù 2
PK - Pakistan 2
TW - Taiwan 2
UZ - Uzbekistan 2
VE - Venezuela 2
ZA - Sudafrica 2
A2 - ???statistics.table.value.countryCode.A2??? 1
AL - Albania 1
AU - Australia 1
BN - Brunei Darussalam 1
CL - Cile 1
DZ - Algeria 1
EG - Egitto 1
GE - Georgia 1
HU - Ungheria 1
JM - Giamaica 1
KG - Kirghizistan 1
KZ - Kazakistan 1
LA - Repubblica Popolare Democratica del Laos 1
MA - Marocco 1
PA - Panama 1
PH - Filippine 1
RS - Serbia 1
TJ - Tagikistan 1
Totale 5.438
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Città #
Turin 419
Singapore 368
Ashburn 179
Chandler 137
Dallas 135
Brussels 119
Santa Clara 115
Milan 106
Seoul 87
Beijing 86
Torino 86
Boardman 62
Dublin 59
Council Bluffs 58
Ann Arbor 57
Hefei 53
Princeton 52
New York 35
Rome 33
Southend 32
Abidjan 30
Berlin 28
Munich 27
Los Angeles 25
Jakarta 24
Bottanuco 21
Piscataway 21
Bremen 18
Istanbul 18
Wilmington 18
Lappeenranta 17
Buffalo 16
Cambridge 16
Verzuolo 16
Genoa 15
Helsinki 14
Nuremberg 14
São Paulo 14
Tokyo 14
Madrid 13
Bologna 12
Bern 11
Oslo 11
San Donato Milanese 11
Barcelona 10
Houston 10
Montreal 10
Redondo Beach 10
Rheinfelden 10
Turku 10
Belo Horizonte 9
Guangzhou 9
Shanghai 9
Amsterdam 8
Atlanta 8
Cangzhou 8
Ljubljana 8
Ne 8
Paris 8
Trento 8
Vienna 8
Yubileyny 8
Borgosesia 7
Brno 7
Columbus 7
Falls Church 7
Moscow 7
Nantes 7
Redmond 7
Redwood City 7
Seattle 7
Toronto 7
Washington 7
Brooklyn 6
Cadoneghe 6
Denver 6
Gif-sur-yvette 6
Moncalieri 6
Mosul 6
Noisy-le-Grand 6
Warsaw 6
Bari 5
Biella 5
Bogotá 5
Boston 5
Brescia 5
Chicago 5
Deruta 5
Frankfurt am Main 5
Fuzhou 5
Hanoi 5
Ho Chi Minh City 5
Izmir 5
London 5
Manhattan 5
Miami 5
Mumbai 5
Novara 5
Padova 5
Palermo 5
Totale 3.081
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Nome #
An OpenFOAM solver for multiphysics modeling of fusion reactor design: The nemoFoam code 223
Neutronic Analysis of the Fusion Reactor ARC: Monte Carlo Simulations with the Serpent Code 222
Neutronic benchmark of the FRENETIC code for the multiphysics analysis of lead fast reactors 221
Methods for safety and stability analysis of nuclear systems 219
Non-intrusive Uncertainty Propagation in the ARC Fusion Reactor through the nemoFOAM Multi-physics Tool 204
Nuclear data uncertainty quantification in the ARC fusion reactor 177
Genetic algorithm-based optimisation of the few-group structure for lead fast reactor analysis 173
A Nonintrusive Nuclear Data Uncertainty Propagation Study for the ARC Fusion Reactor Design 171
Modelling the PbLi flow including tritium transport and permeation with GETTHEM 153
Alternative Weighting Functions for Group Collapsing of Nuclear Data in Lead Fast Reactors Time-dependent Analyses 152
Spectrum features of the eigenvalue formulations in neutron transport 146
Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design (dataset) 138
Coupled modelling of the EBR-II SHRT-45R including photon heat deposition 138
Development of a New Thermal-Hydraulic Module for FRENETIC, a Code for the Multiphysics Analysis of Liquid Metal–Cooled Reactors 137
Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design 135
Eigenvalue Formulations for the PN Approximation to the Neutron Transport Equation 132
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 129
A non-intrusive reduced order model for the characterisation of the spatial power distribution in large thermal reactors 129
Generalized perturbation techniques for uncertainty quantification in lead-cooled fast reactors 128
A generalised eigenvalue formulation for core-design applications 120
Assessment of numerical methods for the evaluation of higher-order harmonics in diffusion theory 120
A Genetic-Driven Optimization of the Energy Grid Structure for Nodal Full-Core Calculations in Lead-Cooled Fast Reactors 119
Neutron multiplication and fissile material distribution in a nuclear reactor 117
STUDY OF THE EIGENVALUE SPECTRA OF THE NEUTRON TRANSPORT PROBLEM IN PN APPROXIMATION 117
A non-intrusive reduced order model for light water reactor core stability analysis 116
On some features of the eigenvalue problem for the PN approximation of the neutron transport equation 113
Monte Carlo modelling of the ARC Breeding Blanket with the Serpent code  111
NUCLEAR DATA UNCERTAINTY QUANTIFICATION IN MOLTEN SALT REACTORS WITH XGPT 108
Code-to-code SIMMER/FRENETIC comparison for the multiphysics simulation of the ALFRED core 105
A non-intrusive reduced order model for the characterisation of the spatial power distribution in large thermal reactors (dataset) 102
Assessment of numerical methods for the evaluation of higher-order harmonics in diffusion theory 99
A non-intrusive reduced order model for neutronic transient analyses of the ALFRED reactor 98
Code-to-code SIMMER/FRENETIC comparison for the neutronic simulation of lead-cooled fast reactors 97
Development of a new Thermal-Hydraulic Module for FRENETIC, a Code for the Multiphysics Analysis of Liquid Metal-Cooled Reactors 92
Convergence acceleration aspects in the solution of the PN neutron transport eigenvalue problem 91
Neutronic analysis of the fusion reactor ARC: Monte Carlo simulations with the Serpent code (dataset) 88
Uncertainty quantification in FRENETIC calculations of ALFRED lead-cooled fast reactor 86
CONVERGENCE LIMITS IN PERTURBATION THEORY 85
Formulation of the Density Eigenvalue Problemin Neutron Transport for Relevant Engineering Applications 84
Fissile distribution and the critical problem of a nuclear reactor: a mathematical approach 83
Generalized Perturbation Techniques for Uncertainty Quantification in Lead-Cooled Fast Reactors (dataset and software) 81
Code-to-code SIMMER/FRENETIC comparison for the neutronic simulation of lead-cooled fast reactors (dataset) 77
Spectrum features of the eigenvalue formulations in neutron transport (dataset) 68
Impact of energy collapsing on the effective neutron lifetime 63
High-precision eigenvalues of the neutron transport equation by the Carlvik method 11
Cross Sections Generation and SPH Correction Methods for Deterministic Code Simulation of the Westinghouse LFR Design 9
A weight window approach for dose rate calculations in Lead-cooled Fast Reactors with OpenMC 8
Designing energy discretisations for sensitivity studies in lead-cooled fast reactors using a genetic algorithm 6
A Monte Carlo Implementation of the ζ-Eigenvalue Equation 4
The Neutronics Codes FENNECS and FRENETIC: Code-to-code Benchmarking on Lead and Sodium-cooled Fast Reactors 3
Impact of energy collapsing on the effective neutron lifetime (dataset) 3
A genetic-driven optimisation of the energy grid structure for nodal full-core calculations in LFR (dataset) 3
Totale 5.614
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Categoria #
all - tutte 17.788
article - articoli 8.204
book - libri 0
conference - conferenze 6.898
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 32.890
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021157 0 0 0 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
2023/2024830 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
2025/20261.360 346 198 378 438 0 0 0 0 0 0 0 0
Totale 5.614