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

PIZZOCRI, DAVIDE
 Distribuzione geografica
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Continente #
NA - Nord America 5.405
EU - Europa 4.544
AS - Asia 3.511
SA - Sud America 568
AF - Africa 221
OC - Oceania 18
Continente sconosciuto - Info sul continente non disponibili 5
Totale 14.272
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Nazione #
US - Stati Uniti d'America 5.267
RU - Federazione Russa 1.757
IT - Italia 1.114
SG - Singapore 1.049
CN - Cina 1.002
BR - Brasile 460
FR - Francia 388
VN - Vietnam 292
KR - Corea 280
JP - Giappone 250
GB - Regno Unito 217
DE - Germania 188
HK - Hong Kong 128
AT - Austria 126
FI - Finlandia 116
NL - Olanda 106
MA - Marocco 98
CA - Canada 82
ES - Italia 81
ID - Indonesia 79
JO - Giordania 71
SE - Svezia 71
IE - Irlanda 67
IN - India 65
BE - Belgio 57
CH - Svizzera 56
BD - Bangladesh 49
ZA - Sudafrica 40
HU - Ungheria 39
MX - Messico 37
AR - Argentina 36
IQ - Iraq 36
UA - Ucraina 36
TR - Turchia 32
PL - Polonia 27
TW - Taiwan 25
CI - Costa d'Avorio 22
IR - Iran 22
PK - Pakistan 17
LT - Lituania 16
SA - Arabia Saudita 16
CL - Cile 15
GR - Grecia 15
AU - Australia 14
EC - Ecuador 14
MY - Malesia 14
RO - Romania 14
AE - Emirati Arabi Uniti 13
CO - Colombia 13
EG - Egitto 12
VE - Venezuela 12
PH - Filippine 11
PY - Paraguay 11
NP - Nepal 10
BJ - Benin 9
AZ - Azerbaigian 8
PT - Portogallo 8
TH - Thailandia 8
UZ - Uzbekistan 8
DK - Danimarca 7
CZ - Repubblica Ceca 6
ET - Etiopia 6
HN - Honduras 6
SK - Slovacchia (Repubblica Slovacca) 6
TN - Tunisia 6
AL - Albania 5
KE - Kenya 5
NG - Nigeria 5
OM - Oman 5
DZ - Algeria 4
IL - Israele 4
NO - Norvegia 4
PS - Palestinian Territory 4
SI - Slovenia 4
SN - Senegal 4
CR - Costa Rica 3
KG - Kirghizistan 3
LI - Liechtenstein 3
PE - Perù 3
TT - Trinidad e Tobago 3
XK - ???statistics.table.value.countryCode.XK??? 3
BO - Bolivia 2
EU - Europa 2
GH - Ghana 2
JM - Giamaica 2
KZ - Kazakistan 2
LB - Libano 2
LV - Lettonia 2
MR - Mauritania 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
BB - Barbados 1
BG - Bulgaria 1
BH - Bahrain 1
BN - Brunei Darussalam 1
Totale 14.257
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Città #
Ashburn 1.040
Singapore 648
San Jose 559
Milan 499
Santa Clara 382
Moscow 277
Seoul 260
Council Bluffs 258
Chandler 255
Fairfield 246
Hefei 244
Tokyo 201
The Dalles 164
Seattle 124
Beijing 116
Dallas 114
Vienna 114
Wilmington 109
Los Angeles 108
Lauterbourg 106
Woodbridge 105
Houston 101
Hong Kong 95
Boardman 84
Ho Chi Minh City 84
Cambridge 82
Ann Arbor 73
Helsinki 71
Amman 70
London 64
New York 63
Dublin 62
Casablanca 58
Jakarta 58
Frankfurt am Main 54
Málaga 53
North Charleston 52
Lawrence 51
Medford 48
São Paulo 48
Hanoi 47
Kent 47
Amsterdam 44
Dearborn 35
Rome 35
Buffalo 33
Brussels 31
Budapest 31
Redwood City 31
Las Vegas 30
Turin 30
Johannesburg 29
Redmond 29
Ottawa 28
Paris 28
Kenitra 27
Shanghai 25
Chicago 24
Guangzhou 24
Stockholm 24
Tortona 24
Munich 23
Orem 23
Columbus 22
Düsseldorf 21
Abidjan 20
Lappeenranta 20
Warsaw 20
Bologna 19
Nuremberg 19
San Diego 18
Mumbai 17
Gif-sur-yvette 16
Rio de Janeiro 16
Brooklyn 15
Da Nang 15
Villelaure 15
Aix-en-Provence 14
Idaho Falls 14
Manchester 14
Norwalk 14
Phoenix 14
Changsha 13
Lausanne 13
Montreal 13
Taipei 13
Zurich 13
Chennai 12
Dong Ket 12
La Tour-de-Peilz 12
Washington 12
Baghdad 11
Belo Horizonte 11
Denver 11
Dhaka 11
Toronto 11
Turku 11
Edinburgh 10
Madrid 10
Portsmouth 10
Totale 8.434
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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 294
Towards multi-physics description of fuel behaviour for accidental conditions 250
Fuel performance simulations of ESNII prototypes: Results on the MYRRHA case study 220
Modelling of Transient Fission Gas Behaviour in Oxide Fuel and Application to the BISON Code 215
Description of new meso-scale models and their implementation in fuel performance codes 214
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
Transient simulation of the in-pile performance of a MA-bearing fuel pin 195
Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant 189
Description of new correlations and databases for fuel performance codes to be applied to Am bearing fuels 188
A semi-empirical model for the formation and depletion of the high burnup structure in UO2 187
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor 186
Spaceship Earth. Space-driven technologies and systems for sustainability on ground 183
Review of available models and progress on the sub-models dealing with the intra- and intergranular inert gas behaviour 183
Properties of the high burnup structure in nuclear light water reactor fuel 180
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
A Physics-Based Description of Inter-Granular Helium Behaviour in SCIANTIX for Application in Fuel Performance Codes 176
IAEA FUMAC BENCHMARK ON THE HALDEN, STUDISVIK AND QUENCH-L1 LOCA TESTS 173
Synthesis of the inert gas behaviour models developed in INSPYRE 173
Fuel pin behaviour under irradiation with high Pu content: Benchmark exercise 172
Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions 169
Report describing the irradiation experiments selected for the assessment of fuel performance codes 168
Final report on rod cladding failure during SGTR 163
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
Results of the applicative benchmark between TRANSURANUS and GERMINAL on the ASTRID case study 156
Data Assimilation for Fuel Performance Code Development: Application to Oxide Fuel Thermal Properties 153
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
Physics-based modelling and validation of inter-granular helium behaviour in SCIANTIX 145
A methodology for accelerated design of irradiation experiments: Demonstration via an OpenFOAM-informed TRANSURANUS simulation 145
Spaceship Earth. Space-Driven Technologies and Systems for Sustainability on Ground 145
Synthesis of the presentation of INSPYRE results to the User Group 144
Development of best estimate numerical tools for LFR design and safety analysis 144
Synthesis of INSPYRE results 142
Greenspace: Towards a Systematic, Global and Innovative Evaluation of the Environmental Impact of Space Activities for a Safe and Sustainable Space Environment 142
Simulation and optimization of performance during normal operating conditions of a minor actinide-bearing fuel pin 142
The SCIANTIX code for fission gas behaviour: Status, upgrades, separate-effect validation, and future developments 140
A modelling methodology for the description of helium behaviour accounting for the grain-size distribution 140
3D reconstruction of two-phase random heterogeneous material from 2D sections: An approach via genetic algorithms 139
A surrogate model for the helium production rate in fast reactor MOX fuels 137
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 of thermal conductivity and melting behaviour of minor actinide-MOX fuels and assessment against experimental and molecular dynamics data 131
Microhardness and Young's modulus of high burn-up UO2 fuel 130
Towards modelling defective fuel rods in TRANSURANUS: Benchmark and assessment of gaseous and volatile radioactive fission product release 129
Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part II: Coupling SCIANTIX with TRANSURANUS 125
Modelling Fission Gas Behaviour with the BISON Fuel Performance Code 125
Best practices and QA protocols for code development 124
OpenFOAM-informed TRANSURANUS simulations for assessing the fuel pin performance in the MYRRHA in-pile test section 123
Advanced interpretation of the SPHERE irradiation experiment with neutronics and fuel performance codes 123
On the use of spectral algorithms for the prediction of short-lived volatile fission product release: Methodology for bounding numerical error 123
Performance analysis and helium behaviour of Am-bearing fuel pins for irradiation in the MYRRHA reactor 123
Integral-scale validation of the SCIANTIX code for Light Water Reactor fuel rods 119
Towards simulations of fuel rod behaviour during severe accidents by coupling TRANSURANUS with SCIANTIX and MFPR-F 118
On the definition of the escape rate coefficient 117
A Continuum Dislocation Dynamics Crystal Plasticity Approach to Irradiated BCC α-Iron 115
Modelling and assessment of thermophysical properties of Am-bearing fuels for transmutation purposes in fast reactors 113
Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients 112
Current Status and Planned Research Activities for the TRANSURANUS Code Application to High Burnup Fuels 109
Improvement of the BISON U3Si2 modeling capabilities based on multiscale developments to modeling fission gas behavior 109
Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part I: SCIANTIX 109
Status and Planned Activities for the SCIANTIX Code Application to High Burnup Fuels 106
Consideration of Cr-doped UO2 fuel performance for a Fluoride-Cooled High Temperature Reactor concept 105
Two-phase modelling for fission gas sweeping in restructuring nuclear oxide fuel 102
Chromia-doped UO2 fuel: An engineering model for chromium solubility and fission gas diffusivity 102
Analysis of the performance of driver MOX fuel in the MYRRHA reactor under Beam Power Jump transient irradiation conditions 102
The AGR-like FHR reactor: Assessing the technical limits of the fuel 99
Modeling LOCA behavior with the BISON fuel performance code 94
Fuel Modelling in Accident Conditions (FUMAC) 94
Third Yearly Activity Report 93
Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation 91
Modeling and Analysis of Nuclear Fuel Pin Behavior for Innovative Lead Cooled FBR 89
PuMMA blind benchmark: Performance of high plutonium content MOX fuel under irradiation 89
SCIANTIX: A new meso-scale module enhancing fuel performance simulations 88
On the intra-granular behaviour of a cocktail of inert gases in oxide nuclear fuel: Methodological recommendation for accelerated experimental investigation 88
Education and Training Plan 86
Synthesis of the First User Group Meeting 86
Modelling and Assessment of Inert Gas Behaviour in UO2 Nuclear Fuel for Transient Analysis 84
Modelling fission gas behaviour in fast reactor (U,Pu)O2 fuel with BISON 82
Supporto alla progettazione del combustibile nucleare per Il reattore LFR 64
Critical assessment of the pore size distribution in the rim region of high burnup UO2 fuels 48
On a physics-based model of grain-boundary bubbles overpressurisation and its effects on fuel fragmentation 36
Totale 14.277
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Categoria #
all - tutte 39.862
article - articoli 23.611
book - libri 0
conference - conferenze 5.082
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 245
Totale 68.800
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021210 0 0 0 0 0 0 0 0 0 77 53 80
2021/2022524 16 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
2025/20267.957 1.396 1.368 443 648 510 475 1.062 457 720 878 0 0
Totale 14.450