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

BARANI, TOMMASO
 Distribuzione geografica
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Continente #
NA - Nord America 3.241
EU - Europa 2.273
AS - Asia 1.282
SA - Sud America 213
AF - Africa 84
Continente sconosciuto - Info sul continente non disponibili 60
OC - Oceania 10
Totale 7.163
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Nazione #
US - Stati Uniti d'America 3.140
RU - Federazione Russa 786
IT - Italia 655
CN - Cina 356
SG - Singapore 341
BR - Brasile 174
FR - Francia 166
GB - Regno Unito 141
VN - Vietnam 113
KR - Corea 92
DE - Germania 88
JP - Giappone 82
AT - Austria 71
FI - Finlandia 62
HK - Hong Kong 59
CA - Canada 58
ES - Italia 55
SE - Svezia 43
NL - Olanda 40
MA - Marocco 39
JO - Giordania 37
ID - Indonesia 35
IN - India 33
IE - Irlanda 32
BD - Bangladesh 27
CH - Svizzera 23
BE - Belgio 21
UA - Ucraina 18
ZA - Sudafrica 18
IR - Iran 17
TR - Turchia 17
AR - Argentina 15
PL - Polonia 15
IQ - Iraq 13
MX - Messico 13
TW - Taiwan 12
LT - Lituania 10
AU - Australia 9
HU - Ungheria 9
SA - Arabia Saudita 9
CO - Colombia 7
DK - Danimarca 7
EG - Egitto 7
JM - Giamaica 7
PK - Pakistan 7
RO - Romania 7
GR - Grecia 6
HN - Honduras 6
EC - Ecuador 5
MY - Malesia 5
NP - Nepal 5
PY - Paraguay 5
UZ - Uzbekistan 5
AE - Emirati Arabi Uniti 4
CR - Costa Rica 4
TT - Trinidad e Tobago 4
CZ - Repubblica Ceca 3
LI - Liechtenstein 3
NG - Nigeria 3
PE - Perù 3
PH - Filippine 3
SN - Senegal 3
TH - Thailandia 3
TN - Tunisia 3
AZ - Azerbaigian 2
BB - Barbados 2
CI - Costa d'Avorio 2
CL - Cile 2
DZ - Algeria 2
EU - Europa 2
KE - Kenya 2
NO - Norvegia 2
OM - Oman 2
PR - Porto Rico 2
RS - Serbia 2
SV - El Salvador 2
VE - Venezuela 2
AL - Albania 1
BG - Bulgaria 1
BJ - Benin 1
CG - Congo 1
CU - Cuba 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
NI - Nicaragua 1
NZ - Nuova Zelanda 1
PA - Panama 1
PT - Portogallo 1
SI - Slovenia 1
SK - Slovacchia (Repubblica Slovacca) 1
SX - ???statistics.table.value.countryCode.SX??? 1
SY - Repubblica araba siriana 1
XK - ???statistics.table.value.countryCode.XK??? 1
Totale 7.107
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Città #
Ashburn 638
San Jose 288
Santa Clara 210
Milan 206
Chandler 199
Singapore 195
Fairfield 159
Council Bluffs 139
Moscow 118
Seoul 83
Seattle 80
The Dalles 76
Vienna 69
Beijing 67
Wilmington 67
Tokyo 64
Houston 60
Los Angeles 58
Dallas 56
Cambridge 55
Woodbridge 55
London 52
Lauterbourg 50
Helsinki 43
Málaga 43
Hong Kong 41
Boardman 40
Amman 37
Hefei 37
Medford 34
Rome 33
Lawrence 32
New York 31
Dublin 29
Phoenix 29
Turin 29
Frankfurt am Main 28
Ho Chi Minh City 28
Jakarta 28
Casablanca 27
Bologna 24
Redmond 23
Ann Arbor 22
Ottawa 19
São Paulo 18
Tortona 17
Brussels 16
Chicago 15
Johannesburg 15
Kent 14
Redwood City 14
Shanghai 14
Buffalo 13
Hanoi 13
Montreal 12
San Diego 12
Warsaw 12
Guangzhou 11
Lappeenranta 11
Mumbai 11
Amsterdam 10
Gif-sur-yvette 10
Norwalk 10
Orem 10
Paris 10
Düsseldorf 9
Edinburgh 9
Idaho Falls 9
Munich 9
Portsmouth 9
San Francisco 9
Washington 9
Brooklyn 8
Chennai 8
Columbus 8
Dearborn 8
Denver 8
Lausanne 8
Naples 8
Stockholm 8
Basingstoke 7
Berlin 7
Boston 7
Kenitra 7
Las Vegas 7
Manchester 7
Nuremberg 7
Taipei 7
Atlanta 6
Baghdad 6
Changsha 6
Charlotte 6
Copenhagen 6
Da Nang 6
Florence 6
La Tour-de-Peilz 6
Miami 6
Mountain View 6
North Charleston 6
Rio de Janeiro 6
Totale 4.224
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Nome #
SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes 341
Development of best estimate numerical tools for LFR design and safety analysis 339
Incorporation and verification of models and properties in fuel performance codes 235
A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools 228
An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions 222
Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations 219
Synthesis of the inert gas behaviour models developed in INSPYRE 215
Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS 211
Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant 210
Review of available models and progress on the sub-models dealing with the intra- and intergranular inert gas behaviour 207
A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U,Pu)O2 for fast reactors 204
Modeling Fission Gas Release and Bubble Evolution in UO2 for Engineering Fuel Rod Analysis 194
Report describing the irradiation experiments selected for the assessment of fuel performance codes 191
Modelling of the Behaviour of Inert Gases In Oxide and Mixed Oxide Nuclear Fuel under Design Basis Accident Conditions 183
Extension and application of the TRANSURANUS code to the normal operating conditions of the MYRRHA reactor 176
Results of the benchmark between pre- and post-INSPYRE code versions on selected experimental cases 175
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications 175
PolyPole-1: An accurate numerical algorithm for intra-granular fission gas release 174
Isotropic softening model for fuel cracking in BISON 173
Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions 172
An effective numerical algorithm for intra-granular fission gas release during non-equilibrium trapping and resolution 171
Towards a physics-based description of intra-granular helium behaviour in oxide fuel for application in fuel performance codes 168
Three-dimensional reconstruction from experimental two-dimensional images: Application to irradiated metallic fuel 168
Numerical and mathematical approaches for computation time reduction 165
Advancement in FGR modeling for transient analysis of FR fuel 165
3D reconstruction of two-phase random heterogeneous material from 2D sections: An approach via genetic algorithms 161
Modeling high burnup structure in oxide fuels for application to fuel performance codes. Part II: Porosity evolution 155
Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment 153
Modelling Fission Gas Behaviour with the BISON Fuel Performance Code 153
Development of best estimate numerical tools for LFR design and safety analysis 153
Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment 152
A reduced order model for fission gas diffusion in columnar grains 152
Modelling of Burst Release in Oxide Fuel and Application to the Transuranus Code 148
Development of best estimate numerical tools for LFR design and safety analysis 141
Status and Planned Activities for the SCIANTIX Code Application to High Burnup Fuels 125
Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients 124
Improvement of the BISON U3Si2 modeling capabilities based on multiscale developments to modeling fission gas behavior 120
Two-phase modelling for fission gas sweeping in restructuring nuclear oxide fuel 117
Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation 102
Modelling fission gas behaviour in fast reactor (U,Pu)O2 fuel with BISON 94
Off-centering effects on MOX fuel behavior 32
Totale 7.163
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Categoria #
all - tutte 21.578
article - articoli 14.182
book - libri 0
conference - conferenze 2.060
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 37.820
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2021/2022244 0 0 0 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
2026/2027562 76 93 209 184 0 0 0 0 0 0 0 0
Totale 7.163