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

BARANI, TOMMASO
 Distribuzione geografica
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Continente #
NA - Nord America 2.648
EU - Europa 2.053
AS - Asia 1.249
SA - Sud America 203
AF - Africa 83
OC - Oceania 10
Continente sconosciuto - Info sul continente non disponibili 3
Totale 6.249
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Nazione #
US - Stati Uniti d'America 2.586
RU - Federazione Russa 786
IT - Italia 455
CN - Cina 353
SG - Singapore 336
BR - Brasile 167
FR - Francia 162
GB - Regno Unito 134
VN - Vietnam 108
KR - Corea 91
DE - Germania 88
JP - Giappone 82
AT - Austria 71
FI - Finlandia 62
ES - Italia 55
HK - Hong Kong 51
CA - Canada 43
SE - Svezia 43
MA - Marocco 39
NL - Olanda 39
JO - Giordania 37
ID - Indonesia 35
IN - India 33
IE - Irlanda 32
BD - Bangladesh 23
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
TW - Taiwan 12
LT - Lituania 10
MX - Messico 10
AU - Australia 9
SA - Arabia Saudita 8
DK - Danimarca 7
EG - Egitto 7
PK - Pakistan 6
RO - Romania 6
CO - Colombia 5
GR - Grecia 5
HU - Ungheria 5
MY - Malesia 5
NP - Nepal 5
PY - Paraguay 5
UZ - Uzbekistan 5
AE - Emirati Arabi Uniti 4
EC - Ecuador 4
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
CZ - Repubblica Ceca 2
DZ - Algeria 2
EU - Europa 2
KE - Kenya 2
NO - Norvegia 2
OM - Oman 2
PR - Porto Rico 2
RS - Serbia 2
TH - Thailandia 2
VE - Venezuela 2
AL - Albania 1
AZ - Azerbaigian 1
BG - Bulgaria 1
BJ - Benin 1
CR - Costa Rica 1
ET - Etiopia 1
GH - Ghana 1
HN - Honduras 1
IL - Israele 1
JM - Giamaica 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 6.249
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Città #
Ashburn 480
San Jose 220
Chandler 199
Singapore 192
Santa Clara 185
Fairfield 159
Milan 141
Council Bluffs 119
Moscow 118
Seoul 82
Seattle 80
The Dalles 76
Vienna 69
Wilmington 66
Beijing 64
Tokyo 64
Houston 58
Cambridge 55
Woodbridge 55
London 52
Dallas 50
Lauterbourg 50
Los Angeles 47
Helsinki 43
Málaga 43
Amman 37
Boardman 37
Hefei 37
Hong Kong 35
Medford 34
Lawrence 32
Dublin 28
Frankfurt am Main 28
Jakarta 28
Casablanca 27
New York 27
Ho Chi Minh City 26
Redmond 23
Ann Arbor 22
Ottawa 19
Turin 19
Tortona 17
Brussels 16
Johannesburg 15
São Paulo 15
Kent 14
Redwood City 14
Rome 14
Shanghai 14
Hanoi 13
Buffalo 12
San Diego 12
Warsaw 12
Chicago 11
Guangzhou 11
Lappeenranta 11
Mumbai 11
Amsterdam 10
Bologna 10
Gif-sur-yvette 10
Orem 10
Paris 10
Düsseldorf 9
Edinburgh 9
Idaho Falls 9
Montreal 9
Munich 9
Norwalk 9
Chennai 8
Columbus 8
Dearborn 8
Lausanne 8
Portsmouth 8
Stockholm 8
Washington 8
Basingstoke 7
Berlin 7
Boston 7
Brooklyn 7
Kenitra 7
Nuremberg 7
Taipei 7
Baghdad 6
Changsha 6
Copenhagen 6
Da Nang 6
La Tour-de-Peilz 6
Miami 6
Mountain View 6
North Charleston 6
Rio de Janeiro 6
Toronto 6
Alexandria 5
Atlanta 5
Como 5
Dong Ket 5
Harbin 5
Phoenix 5
Pisa 5
Tashkent 5
Totale 3.747
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Nome #
Development of best estimate numerical tools for LFR design and safety analysis 313
SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes 295
An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions 210
Incorporation and verification of models and properties in fuel performance codes 209
A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools 208
Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS 198
Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations 196
Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant 189
Review of available models and progress on the sub-models dealing with the intra- and intergranular inert gas behaviour 183
A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U,Pu)O2 for fast reactors 180
Modeling Fission Gas Release and Bubble Evolution in UO2 for Engineering Fuel Rod Analysis 178
Synthesis of the inert gas behaviour models developed in INSPYRE 173
Report describing the irradiation experiments selected for the assessment of fuel performance codes 168
Modelling of the Behaviour of Inert Gases In Oxide and Mixed Oxide Nuclear Fuel under Design Basis Accident Conditions 163
Isotropic softening model for fuel cracking in BISON 160
An effective numerical algorithm for intra-granular fission gas release during non-equilibrium trapping and resolution 159
PolyPole-1: An accurate numerical algorithm for intra-granular fission gas release 158
Extension and application of the TRANSURANUS code to the normal operating conditions of the MYRRHA reactor 158
Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions 153
Three-dimensional reconstruction from experimental two-dimensional images: Application to irradiated metallic fuel 150
Results of the benchmark between pre- and post-INSPYRE code versions on selected experimental cases 149
Development of best estimate numerical tools for LFR design and safety analysis 144
3D reconstruction of two-phase random heterogeneous material from 2D sections: An approach via genetic algorithms 139
Modeling high burnup structure in oxide fuels for application to fuel performance codes. Part II: Porosity evolution 137
A reduced order model for fission gas diffusion in columnar grains 136
Towards a physics-based description of intra-granular helium behaviour in oxide fuel for application in fuel performance codes 135
Numerical and mathematical approaches for computation time reduction 134
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications 134
Modelling of Burst Release in Oxide Fuel and Application to the Transuranus Code 133
Development of best estimate numerical tools for LFR design and safety analysis 133
Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment 132
Advancement in FGR modeling for transient analysis of FR fuel 132
Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment 132
Modelling Fission Gas Behaviour with the BISON Fuel Performance Code 125
Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients 112
Improvement of the BISON U3Si2 modeling capabilities based on multiscale developments to modeling fission gas behavior 109
Status and Planned Activities for the SCIANTIX Code Application to High Burnup Fuels 106
Two-phase modelling for fission gas sweeping in restructuring nuclear oxide fuel 102
Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation 91
Modelling fission gas behaviour in fast reactor (U,Pu)O2 fuel with BISON 82
Off-centering effects on MOX fuel behavior 6
Totale 6.304
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Categoria #
all - tutte 18.633
article - articoli 12.321
book - libri 0
conference - conferenze 1.711
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 32.665
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021155 0 0 0 0 0 0 0 0 0 59 43 53
2021/2022330 14 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
2025/20263.001 610 532 125 247 207 175 406 184 199 316 0 0
Totale 6.304