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

PIZZOCRI, DAVIDE
 Distribuzione geografica
Salva come PNG Salva come JPEG
Continente #
NA - Nord America 6.109
EU - Europa 5.155
AS - Asia 3.591
SA - Sud America 573
AF - Africa 221
Continente sconosciuto - Info sul continente non disponibili 189
OC - Oceania 18
Totale 15.856
Salva come PNG Salva come JPEG
Nazione #
US - Stati Uniti d'America 5.911
RU - Federazione Russa 1.757
IT - Italia 1.668
SG - Singapore 1.057
CN - Cina 1.014
BR - Brasile 464
FR - Francia 407
VN - Vietnam 319
KR - Corea 281
JP - Giappone 251
GB - Regno Unito 227
DE - Germania 194
HK - Hong Kong 136
AT - Austria 126
FI - Finlandia 116
NL - Olanda 113
CA - Canada 110
MA - Marocco 98
ES - Italia 81
ID - Indonesia 81
SE - Svezia 73
JO - Giordania 71
IN - India 70
IE - Irlanda 67
BD - Bangladesh 63
BE - Belgio 59
CH - Svizzera 58
HU - Ungheria 44
MX - Messico 40
ZA - Sudafrica 40
AR - Argentina 36
IQ - Iraq 36
UA - Ucraina 36
TR - Turchia 32
PL - Polonia 28
TW - Taiwan 25
CI - Costa d'Avorio 22
IR - Iran 22
PK - Pakistan 18
CL - Cile 16
GR - Grecia 16
LT - Lituania 16
SA - Arabia Saudita 16
RO - Romania 15
AU - Australia 14
EC - Ecuador 14
MY - Malesia 14
AE - Emirati Arabi Uniti 13
CO - Colombia 13
EG - Egitto 12
VE - Venezuela 12
CR - Costa Rica 11
PH - Filippine 11
PY - Paraguay 11
HN - Honduras 10
NP - Nepal 10
BJ - Benin 9
AZ - Azerbaigian 8
JM - Giamaica 8
PT - Portogallo 8
TH - Thailandia 8
UZ - Uzbekistan 8
CZ - Repubblica Ceca 7
DK - Danimarca 7
ET - Etiopia 6
SK - Slovacchia (Repubblica Slovacca) 6
TN - Tunisia 6
AL - Albania 5
IL - Israele 5
KE - Kenya 5
NG - Nigeria 5
OM - Oman 5
TT - Trinidad e Tobago 5
DZ - Algeria 4
NO - Norvegia 4
PS - Palestinian Territory 4
SI - Slovenia 4
SN - Senegal 4
KG - Kirghizistan 3
LI - Liechtenstein 3
PE - Perù 3
SV - El Salvador 3
XK - ???statistics.table.value.countryCode.XK??? 3
BB - Barbados 2
BO - Bolivia 2
EU - Europa 2
GH - Ghana 2
KZ - Kazakistan 2
LB - Libano 2
LV - Lettonia 2
MR - Mauritania 2
NI - Nicaragua 2
NZ - Nuova Zelanda 2
PR - Porto Rico 2
RS - Serbia 2
UY - Uruguay 2
ZW - Zimbabwe 2
AF - Afghanistan, Repubblica islamica di 1
AO - Angola 1
BG - Bulgaria 1
Totale 15.652
Salva come PNG Salva come JPEG
Città #
Ashburn 1.160
Milan 792
Singapore 653
San Jose 636
Santa Clara 407
Council Bluffs 323
Moscow 277
Seoul 261
Chandler 255
Fairfield 246
Hefei 244
Tokyo 202
The Dalles 164
Seattle 124
Beijing 119
Dallas 119
Los Angeles 117
Vienna 114
Wilmington 110
Boardman 107
Lauterbourg 106
Woodbridge 106
Houston 105
Hong Kong 101
Ho Chi Minh City 90
Rome 87
Cambridge 83
Ann Arbor 73
New York 73
Helsinki 71
Amman 70
London 65
Dublin 62
Hanoi 59
Casablanca 58
Jakarta 58
Bologna 57
Frankfurt am Main 54
Málaga 53
North Charleston 52
Lawrence 51
São Paulo 49
Kent 48
Medford 48
Amsterdam 44
Turin 41
Buffalo 36
Dearborn 35
Las Vegas 34
Budapest 33
Brussels 31
Redwood City 31
Johannesburg 29
Redmond 29
Ottawa 28
Paris 28
Shanghai 28
Kenitra 27
Chicago 25
Munich 25
Orem 25
Phoenix 25
Guangzhou 24
Stockholm 24
Tortona 24
Columbus 22
Düsseldorf 21
Warsaw 21
Abidjan 20
Lappeenranta 20
Nuremberg 19
Brooklyn 18
Manchester 18
San Diego 18
Montreal 17
Mumbai 17
Gif-sur-yvette 16
Rio de Janeiro 16
Da Nang 15
Denver 15
Naples 15
San Francisco 15
Toronto 15
Villelaure 15
Aix-en-Provence 14
Idaho Falls 14
Norwalk 14
Washington 14
Changsha 13
Lausanne 13
Taipei 13
Zurich 13
Chennai 12
Dong Ket 12
Grenoble 12
La Tour-de-Peilz 12
Baghdad 11
Belo Horizonte 11
Dhaka 11
Jacksonville 11
Totale 9.268
Salva come PNG Salva come JPEG
Nome #
Towards multi-physics description of fuel behaviour for accidental conditions 332
Development of best estimate numerical tools for LFR design and safety analysis 332
SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes 322
Transient simulation of the in-pile performance of a MA-bearing fuel pin 278
Incorporation and verification of models and properties in fuel performance codes 232
Fuel performance simulations of ESNII prototypes: Results on the MYRRHA case study 230
Description of new meso-scale models and their implementation in fuel performance codes 228
Modelling of Transient Fission Gas Behaviour in Oxide Fuel and Application to the BISON Code 225
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 214
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 203
A semi-empirical model for the formation and depletion of the high burnup structure in UO2 200
Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant 199
Description of new correlations and databases for fuel performance codes to be applied to Am bearing fuels 195
Synthesis of the inert gas behaviour models developed in INSPYRE 195
Review of available models and progress on the sub-models dealing with the intra- and intergranular inert gas behaviour 195
A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U,Pu)O2 for fast reactors 195
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor 194
Spaceship Earth. Space-driven technologies and systems for sustainability on ground 194
Properties of the high burnup structure in nuclear light water reactor fuel 190
Modeling Fission Gas Release and Bubble Evolution in UO2 for Engineering Fuel Rod Analysis 189
A Physics-Based Description of Inter-Granular Helium Behaviour in SCIANTIX for Application in Fuel Performance Codes 189
Report describing the irradiation experiments selected for the assessment of fuel performance codes 186
IAEA FUMAC BENCHMARK ON THE HALDEN, STUDISVIK AND QUENCH-L1 LOCA TESTS 184
Fuel pin behaviour under irradiation with high Pu content: Benchmark exercise 180
Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions 179
Data Assimilation for Fuel Performance Code Development: Application to Oxide Fuel Thermal Properties 178
Final report on rod cladding failure during SGTR 172
Modelling of the Behaviour of Inert Gases In Oxide and Mixed Oxide Nuclear Fuel under Design Basis Accident Conditions 172
Synthesis of INSPYRE results 168
Results of the applicative benchmark between TRANSURANUS and GERMINAL on the ASTRID case study 168
Isotropic softening model for fuel cracking in BISON 167
PolyPole-1: An accurate numerical algorithm for intra-granular fission gas release 166
An effective numerical algorithm for intra-granular fission gas release during non-equilibrium trapping and resolution 166
Results of the benchmark between pre- and post-INSPYRE code versions on selected experimental cases 165
Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions 165
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications 164
Extension and application of the TRANSURANUS code to the normal operating conditions of the MYRRHA reactor 163
Synthesis of the presentation of INSPYRE results to the User Group 161
The SCIANTIX code for fission gas behaviour: Status, upgrades, separate-effect validation, and future developments 160
Greenspace: Towards a Systematic, Global and Innovative Evaluation of the Environmental Impact of Space Activities for a Safe and Sustainable Space Environment 157
Physics-based modelling and validation of inter-granular helium behaviour in SCIANTIX 156
Three-dimensional reconstruction from experimental two-dimensional images: Application to irradiated metallic fuel 156
Simulation and optimization of performance during normal operating conditions of a minor actinide-bearing fuel pin 156
Numerical and mathematical approaches for computation time reduction 155
Towards a physics-based description of intra-granular helium behaviour in oxide fuel for application in fuel performance codes 155
A modelling methodology for the description of helium behaviour accounting for the grain-size distribution 155
3D reconstruction of two-phase random heterogeneous material from 2D sections: An approach via genetic algorithms 154
A methodology for accelerated design of irradiation experiments: Demonstration via an OpenFOAM-informed TRANSURANUS simulation 152
Microhardness and Young's modulus of high burn-up UO2 fuel 152
Development of best estimate numerical tools for LFR design and safety analysis 151
Spaceship Earth. Space-Driven Technologies and Systems for Sustainability on Ground 150
Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment 146
Modelling of Burst Release in Oxide Fuel and Application to the Transuranus Code 145
Modeling high burnup structure in oxide fuels for application to fuel performance codes. Part II: Porosity evolution 145
A reduced order model for fission gas diffusion in columnar grains 144
Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment 143
A surrogate model for the helium production rate in fast reactor MOX fuels 143
Towards modelling defective fuel rods in TRANSURANUS: Benchmark and assessment of gaseous and volatile radioactive fission product release 139
Modelling of thermal conductivity and melting behaviour of minor actinide-MOX fuels and assessment against experimental and molecular dynamics data 139
OpenFOAM-informed TRANSURANUS simulations for assessing the fuel pin performance in the MYRRHA in-pile test section 137
Advancement in FGR modeling for transient analysis of FR fuel 137
Development of best estimate numerical tools for LFR design and safety analysis 136
Best practices and QA protocols for code development 135
On the use of spectral algorithms for the prediction of short-lived volatile fission product release: Methodology for bounding numerical error 133
Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part II: Coupling SCIANTIX with TRANSURANUS 132
Performance analysis and helium behaviour of Am-bearing fuel pins for irradiation in the MYRRHA reactor 131
Modelling Fission Gas Behaviour with the BISON Fuel Performance Code 129
On the definition of the escape rate coefficient 127
Advanced interpretation of the SPHERE irradiation experiment with neutronics and fuel performance codes 127
Towards simulations of fuel rod behaviour during severe accidents by coupling TRANSURANUS with SCIANTIX and MFPR-F 126
Integral-scale validation of the SCIANTIX code for Light Water Reactor fuel rods 125
Modelling and assessment of thermophysical properties of Am-bearing fuels for transmutation purposes in fast reactors 123
A Continuum Dislocation Dynamics Crystal Plasticity Approach to Irradiated BCC α-Iron 119
Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients 117
Current Status and Planned Research Activities for the TRANSURANUS Code Application to High Burnup Fuels 116
Consideration of Cr-doped UO2 fuel performance for a Fluoride-Cooled High Temperature Reactor concept 114
Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part I: SCIANTIX 114
Improvement of the BISON U3Si2 modeling capabilities based on multiscale developments to modeling fission gas behavior 113
Analysis of the performance of driver MOX fuel in the MYRRHA reactor under Beam Power Jump transient irradiation conditions 113
The AGR-like FHR reactor: Assessing the technical limits of the fuel 112
Status and Planned Activities for the SCIANTIX Code Application to High Burnup Fuels 111
Chromia-doped UO2 fuel: An engineering model for chromium solubility and fission gas diffusivity 111
Two-phase modelling for fission gas sweeping in restructuring nuclear oxide fuel 109
Modeling LOCA behavior with the BISON fuel performance code 101
Modeling and Analysis of Nuclear Fuel Pin Behavior for Innovative Lead Cooled FBR 101
On the intra-granular behaviour of a cocktail of inert gases in oxide nuclear fuel: Methodological recommendation for accelerated experimental investigation 101
PuMMA blind benchmark: Performance of high plutonium content MOX fuel under irradiation 101
Third Yearly Activity Report 99
Synthesis of the First User Group Meeting 96
Fuel Modelling in Accident Conditions (FUMAC) 95
SCIANTIX: A new meso-scale module enhancing fuel performance simulations 94
Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation 94
Education and Training Plan 93
Modelling and Assessment of Inert Gas Behaviour in UO2 Nuclear Fuel for Transient Analysis 92
Modelling fission gas behaviour in fast reactor (U,Pu)O2 fuel with BISON 86
Supporto alla progettazione del combustibile nucleare per Il reattore LFR 77
On a physics-based model of grain-boundary bubbles overpressurisation and its effects on fuel fragmentation 51
Critical assessment of the pore size distribution in the rim region of high burnup UO2 fuels 51
Totale 15.491
Salva come PNG Salva come JPEG
Categoria #
all - tutte 45.603
article - articoli 26.767
book - libri 0
conference - conferenze 5.745
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 264
Totale 78.379
Salva come PNG Salva come JPEG


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2021/2022508 0 70 40 38 24 22 29 30 36 28 114 77
2022/20231.028 69 58 54 73 92 109 28 72 201 98 102 72
2023/2024770 43 84 36 49 61 88 86 82 44 50 64 83
2024/20252.662 57 44 52 79 403 348 243 212 293 142 351 438
2025/20268.883 1.396 1.368 443 648 510 475 1.062 457 720 918 311 575
2026/2027480 310 170 0 0 0 0 0 0 0 0 0 0
Totale 15.856