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

BARANI, TOMMASO
 Distribuzione geografica
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Continente #
NA - Nord America 2.766
EU - Europa 2.098
AS - Asia 1.256
SA - Sud America 203
AF - Africa 83
OC - Oceania 10
Continente sconosciuto - Info sul continente non disponibili 3
Totale 6.419
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Nazione #
US - Stati Uniti d'America 2.700
RU - Federazione Russa 786
IT - Italia 490
CN - Cina 354
SG - Singapore 338
BR - Brasile 167
FR - Francia 165
GB - Regno Unito 138
VN - Vietnam 108
KR - Corea 91
DE - Germania 88
JP - Giappone 82
AT - Austria 71
FI - Finlandia 62
ES - Italia 55
HK - Hong Kong 54
CA - Canada 44
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
MX - Messico 12
TW - Taiwan 12
LT - Lituania 10
AU - Australia 9
SA - Arabia Saudita 8
DK - Danimarca 7
EG - Egitto 7
HU - Ungheria 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
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
HN - Honduras 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
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 6.419
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Città #
Ashburn 502
San Jose 241
Chandler 199
Santa Clara 197
Singapore 194
Fairfield 159
Milan 151
Council Bluffs 120
Moscow 118
Seoul 82
Seattle 80
The Dalles 76
Vienna 69
Wilmington 67
Beijing 65
Tokyo 64
Houston 58
Cambridge 55
Woodbridge 55
Dallas 52
London 52
Lauterbourg 50
Los Angeles 50
Helsinki 43
Málaga 43
Boardman 39
Hong Kong 38
Amman 37
Hefei 37
Medford 34
Lawrence 32
New York 29
Dublin 28
Frankfurt am Main 28
Jakarta 28
Casablanca 27
Ho Chi Minh City 26
Redmond 23
Ann Arbor 22
Bologna 22
Turin 22
Ottawa 19
Tortona 17
Brussels 16
Johannesburg 15
São Paulo 15
Kent 14
Redwood City 14
Rome 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
Chennai 8
Columbus 8
Dearborn 8
Lausanne 8
Portsmouth 8
Stockholm 8
Washington 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
La Tour-de-Peilz 6
Miami 6
Mountain View 6
North Charleston 6
Rio de Janeiro 6
Toronto 6
Alexandria 5
Budapest 5
Como 5
Denver 5
Totale 3.852
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Nome #
Development of best estimate numerical tools for LFR design and safety analysis 319
SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes 305
Incorporation and verification of models and properties in fuel performance codes 221
An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions 212
A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools 210
Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS 201
Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations 200
Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant 191
Review of available models and progress on the sub-models dealing with the intra- and intergranular inert gas behaviour 188
A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U,Pu)O2 for fast reactors 188
Modeling Fission Gas Release and Bubble Evolution in UO2 for Engineering Fuel Rod Analysis 183
Synthesis of the inert gas behaviour models developed in INSPYRE 181
Report describing the irradiation experiments selected for the assessment of fuel performance codes 175
Modelling of the Behaviour of Inert Gases In Oxide and Mixed Oxide Nuclear Fuel under Design Basis Accident Conditions 163
PolyPole-1: An accurate numerical algorithm for intra-granular fission gas release 162
Isotropic softening model for fuel cracking in BISON 161
An effective numerical algorithm for intra-granular fission gas release during non-equilibrium trapping and resolution 161
Extension and application of the TRANSURANUS code to the normal operating conditions of the MYRRHA reactor 160
Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions 159
Results of the benchmark between pre- and post-INSPYRE code versions on selected experimental cases 157
Three-dimensional reconstruction from experimental two-dimensional images: Application to irradiated metallic fuel 153
3D reconstruction of two-phase random heterogeneous material from 2D sections: An approach via genetic algorithms 149
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications 148
Development of best estimate numerical tools for LFR design and safety analysis 147
Numerical and mathematical approaches for computation time reduction 146
Towards a physics-based description of intra-granular helium behaviour in oxide fuel for application in fuel performance codes 139
Modeling high burnup structure in oxide fuels for application to fuel performance codes. Part II: Porosity evolution 139
Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment 138
A reduced order model for fission gas diffusion in columnar grains 138
Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment 135
Modelling of Burst Release in Oxide Fuel and Application to the Transuranus Code 135
Development of best estimate numerical tools for LFR design and safety analysis 134
Advancement in FGR modeling for transient analysis of FR fuel 133
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 112
Status and Planned Activities for the SCIANTIX Code Application to High Burnup Fuels 110
Improvement of the BISON U3Si2 modeling capabilities based on multiscale developments to modeling fission gas behavior 110
Two-phase modelling for fission gas sweeping in restructuring nuclear oxide fuel 103
Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation 92
Modelling fission gas behaviour in fast reactor (U,Pu)O2 fuel with BISON 83
Off-centering effects on MOX fuel behavior 7
Totale 6.474
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Categoria #
all - tutte 19.634
article - articoli 12.964
book - libri 0
conference - conferenze 1.837
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 34.435
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/202153 0 0 0 0 0 0 0 0 0 0 0 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
2025/20263.171 610 532 125 247 207 175 406 184 199 337 105 44
Totale 6.474