RE.PUBLIC@POLIMI pubblicazioni di ricerca del Politecnico di Milano

BARANI, TOMMASO
 Distribuzione geografica
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Continente #
NA - Nord America 2.866
EU - Europa 2.204
AS - Asia 1.267
SA - Sud America 204
AF - Africa 83
Continente sconosciuto - Info sul continente non disponibili 58
OC - Oceania 10
Totale 6.692
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Nazione #
US - Stati Uniti d'America 2.792
RU - Federazione Russa 786
IT - Italia 593
CN - Cina 355
SG - Singapore 339
BR - Brasile 168
FR - Francia 165
GB - Regno Unito 138
VN - Vietnam 113
KR - Corea 91
DE - Germania 88
JP - Giappone 82
AT - Austria 71
FI - Finlandia 62
HK - Hong Kong 56
ES - Italia 55
CA - Canada 45
SE - Svezia 43
MA - Marocco 39
NL - Olanda 39
JO - Giordania 37
ID - Indonesia 35
IN - India 33
IE - Irlanda 32
BD - Bangladesh 25
CH - Svizzera 22
BE - Belgio 21
UA - Ucraina 18
ZA - Sudafrica 18
IR - Iran 17
AR - Argentina 15
PL - Polonia 15
TR - Turchia 15
IQ - Iraq 12
MX - Messico 12
TW - Taiwan 12
LT - Lituania 10
AU - Australia 9
HU - Ungheria 9
SA - Arabia Saudita 8
DK - Danimarca 7
EG - Egitto 7
PK - Pakistan 7
GR - Grecia 6
RO - Romania 6
CO - Colombia 5
MY - Malesia 5
NP - Nepal 5
PY - Paraguay 5
UZ - Uzbekistan 5
AE - Emirati Arabi Uniti 4
EC - Ecuador 4
HN - Honduras 4
CR - Costa Rica 3
CZ - Repubblica Ceca 3
LI - Liechtenstein 3
NG - Nigeria 3
PE - Perù 3
PH - Filippine 3
SN - Senegal 3
TN - Tunisia 3
TT - Trinidad e Tobago 3
CI - Costa d'Avorio 2
CL - Cile 2
DZ - Algeria 2
EU - Europa 2
JM - Giamaica 2
KE - Kenya 2
NO - Norvegia 2
OM - Oman 2
PR - Porto Rico 2
RS - Serbia 2
SV - El Salvador 2
TH - Thailandia 2
VE - Venezuela 2
AL - Albania 1
AZ - Azerbaigian 1
BG - Bulgaria 1
BJ - Benin 1
ET - Etiopia 1
GH - Ghana 1
IL - Israele 1
KZ - Kazakistan 1
LU - Lussemburgo 1
LV - Lettonia 1
MT - Malta 1
MU - Mauritius 1
NZ - Nuova Zelanda 1
PA - Panama 1
PT - Portogallo 1
SI - Slovenia 1
SK - Slovacchia (Repubblica Slovacca) 1
SY - Repubblica araba siriana 1
XK - ???statistics.table.value.countryCode.XK??? 1
Totale 6.637
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Città #
Ashburn 519
San Jose 252
Chandler 199
Santa Clara 199
Singapore 194
Milan 188
Fairfield 159
Council Bluffs 127
Moscow 118
Seoul 82
Seattle 80
The Dalles 76
Vienna 69
Wilmington 67
Beijing 66
Tokyo 64
Houston 58
Cambridge 55
Woodbridge 55
Los Angeles 54
Dallas 52
London 52
Lauterbourg 50
Helsinki 43
Málaga 43
Boardman 39
Hong Kong 39
Amman 37
Hefei 37
Medford 34
Lawrence 32
Rome 32
New York 29
Dublin 28
Frankfurt am Main 28
Ho Chi Minh City 28
Jakarta 28
Casablanca 27
Turin 25
Bologna 24
Redmond 23
Ann Arbor 22
Ottawa 19
Tortona 17
Brussels 16
Johannesburg 15
São Paulo 15
Kent 14
Redwood City 14
Shanghai 14
Buffalo 13
Hanoi 13
San Diego 12
Warsaw 12
Chicago 11
Guangzhou 11
Lappeenranta 11
Mumbai 11
Amsterdam 10
Gif-sur-yvette 10
Orem 10
Paris 10
Düsseldorf 9
Edinburgh 9
Idaho Falls 9
Montreal 9
Munich 9
Norwalk 9
Washington 9
Chennai 8
Columbus 8
Dearborn 8
Lausanne 8
Portsmouth 8
Stockholm 8
Basingstoke 7
Berlin 7
Boston 7
Brooklyn 7
Kenitra 7
Manchester 7
Nuremberg 7
Phoenix 7
San Francisco 7
Taipei 7
Atlanta 6
Baghdad 6
Changsha 6
Copenhagen 6
Da Nang 6
Denver 6
La Tour-de-Peilz 6
Miami 6
Mountain View 6
North Charleston 6
Rio de Janeiro 6
Toronto 6
Verona 6
Alexandria 5
Budapest 5
Totale 3.960
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Nome #
Development of best estimate numerical tools for LFR design and safety analysis 329
SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes 318
Incorporation and verification of models and properties in fuel performance codes 228
A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools 215
An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions 213
Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations 209
Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS 201
Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant 198
A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U,Pu)O2 for fast reactors 195
Synthesis of the inert gas behaviour models developed in INSPYRE 193
Review of available models and progress on the sub-models dealing with the intra- and intergranular inert gas behaviour 193
Modeling Fission Gas Release and Bubble Evolution in UO2 for Engineering Fuel Rod Analysis 187
Report describing the irradiation experiments selected for the assessment of fuel performance codes 185
Modelling of the Behaviour of Inert Gases In Oxide and Mixed Oxide Nuclear Fuel under Design Basis Accident Conditions 169
PolyPole-1: An accurate numerical algorithm for intra-granular fission gas release 166
Isotropic softening model for fuel cracking in BISON 165
Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions 165
Results of the benchmark between pre- and post-INSPYRE code versions on selected experimental cases 163
An effective numerical algorithm for intra-granular fission gas release during non-equilibrium trapping and resolution 163
Extension and application of the TRANSURANUS code to the normal operating conditions of the MYRRHA reactor 163
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications 162
Three-dimensional reconstruction from experimental two-dimensional images: Application to irradiated metallic fuel 155
Numerical and mathematical approaches for computation time reduction 154
3D reconstruction of two-phase random heterogeneous material from 2D sections: An approach via genetic algorithms 154
Towards a physics-based description of intra-granular helium behaviour in oxide fuel for application in fuel performance codes 153
Development of best estimate numerical tools for LFR design and safety analysis 149
Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment 144
Modeling high burnup structure in oxide fuels for application to fuel performance codes. Part II: Porosity evolution 144
Modelling of Burst Release in Oxide Fuel and Application to the Transuranus Code 142
A reduced order model for fission gas diffusion in columnar grains 142
Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment 140
Advancement in FGR modeling for transient analysis of FR fuel 136
Development of best estimate numerical tools for LFR design and safety analysis 135
Modelling Fission Gas Behaviour with the BISON Fuel Performance Code 126
Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients 115
Improvement of the BISON U3Si2 modeling capabilities based on multiscale developments to modeling fission gas behavior 112
Status and Planned Activities for the SCIANTIX Code Application to High Burnup Fuels 111
Two-phase modelling for fission gas sweeping in restructuring nuclear oxide fuel 108
Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation 94
Modelling fission gas behaviour in fast reactor (U,Pu)O2 fuel with BISON 86
Off-centering effects on MOX fuel behavior 12
Totale 6.692
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Categoria #
all - tutte 20.346
article - articoli 13.415
book - libri 0
conference - conferenze 1.914
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 35.675
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2021/2022316 0 46 26 23 14 15 19 22 20 20 67 44
2022/2023682 44 43 43 51 66 81 14 53 116 70 58 43
2023/2024344 32 46 16 20 38 49 25 21 12 25 23 37
2024/20251.122 25 18 23 42 200 135 69 91 119 67 164 169
2025/20263.298 610 532 125 247 207 175 406 184 199 337 105 171
2026/202791 76 15 0 0 0 0 0 0 0 0 0 0
Totale 6.692