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

PIZZOCRI, DAVIDE
 Distribuzione geografica
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Continente #
NA - Nord America 2.062
EU - Europa 1.309
AS - Asia 413
AF - Africa 47
SA - Sud America 15
OC - Oceania 7
Continente sconosciuto - Info sul continente non disponibili 2
Totale 3.855
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Nazione #
US - Stati Uniti d'America 2.019
IT - Italia 520
FR - Francia 125
CN - Cina 105
GB - Regno Unito 85
FI - Finlandia 81
SG - Singapore 78
ES - Italia 63
JO - Giordania 63
AT - Austria 62
DE - Germania 58
IE - Irlanda 52
SE - Svezia 52
VN - Vietnam 52
CH - Svizzera 42
BE - Belgio 35
CA - Canada 32
UA - Ucraina 31
JP - Giappone 25
HU - Ungheria 24
HK - Hong Kong 22
NL - Olanda 20
IR - Iran 17
KR - Corea 16
RU - Federazione Russa 16
ZA - Sudafrica 16
IN - India 10
MX - Messico 10
BJ - Benin 9
RO - Romania 9
BR - Brasile 7
DK - Danimarca 7
AU - Australia 6
CI - Costa d'Avorio 6
CL - Cile 6
EG - Egitto 6
GR - Grecia 6
TR - Turchia 5
BD - Bangladesh 4
NG - Nigeria 4
PL - Polonia 4
PT - Portogallo 4
LI - Liechtenstein 3
MY - Malesia 3
NO - Norvegia 3
PK - Pakistan 3
SA - Arabia Saudita 3
AE - Emirati Arabi Uniti 2
CO - Colombia 2
EU - Europa 2
TW - Taiwan 2
ZW - Zimbabwe 2
AZ - Azerbaigian 1
BG - Bulgaria 1
CR - Costa Rica 1
CZ - Repubblica Ceca 1
ET - Etiopia 1
GH - Ghana 1
HR - Croazia 1
IL - Israele 1
LT - Lituania 1
LU - Lussemburgo 1
MA - Marocco 1
MT - Malta 1
MU - Mauritius 1
NZ - Nuova Zelanda 1
OM - Oman 1
RS - Serbia 1
Totale 3.855
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Città #
Chandler 255
Fairfield 246
Milan 196
Ashburn 139
Seattle 109
Wilmington 105
Woodbridge 104
Houston 93
Cambridge 82
Ann Arbor 73
Amman 63
Vienna 59
Helsinki 57
Málaga 53
Lawrence 51
Dublin 50
Medford 47
Singapore 44
Dearborn 35
New York 34
Redwood City 31
Redmond 29
Ottawa 26
Tortona 24
Brussels 23
Budapest 23
London 22
Los Angeles 22
Beijing 21
Rome 20
San Diego 18
Gif-sur-yvette 16
Johannesburg 16
Norwalk 14
Aix-en-Provence 12
Amsterdam 12
Columbus 12
Dong Ket 12
La Tour-de-Peilz 12
Tokyo 11
Bologna 10
Lappeenranta 10
Shanghai 10
Cotonou 9
Gainesville 9
Lausanne 9
Mountain View 9
Princeton 9
College Station 8
Edinburgh 8
Hefei 8
Paris 8
San Jose 8
Turin 8
Washington 8
Berlin 7
Idaho Falls 7
Madrid 7
Mumbai 7
Munich 7
Stockholm 7
Abidjan 6
Bordeaux 6
Concepción 6
Copenhagen 6
Grenoble 6
Guangzhou 6
Lancaster 6
Nanterre 6
São Paulo 6
Central 5
Chicago 5
Como 5
Des Moines 5
Genoa 5
Harbin 5
Hillsboro 5
Hong Kong 5
Jacksonville 5
Kyiv 5
Marseille 5
Pisa 5
Santa Clara 5
Seoul 5
Torino 5
Zurich 5
Bovisio Masciago 4
Buc 4
Bucharest 4
Cortenuova 4
Dhaka 4
Le Pecq 4
Le Pontet 4
Phoenix 4
Rousset-les-Vignes 4
Vinon-sur-Verdon 4
Alexandria 3
Altamura 3
Bareggio 3
Chabahar 3
Totale 2.630
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Nome #
SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes 173
Spaceship Earth. Space-driven technologies and systems for sustainability on ground 125
An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions 111
Modelling of Transient Fission Gas Behaviour in Oxide Fuel and Application to the BISON Code 109
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor 109
Development of best estimate numerical tools for LFR design and safety analysis 109
Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS 104
PolyPole-1: An accurate numerical algorithm for intra-granular fission gas release 103
A semi-empirical model for the formation and depletion of the high burnup structure in UO2 97
Greenspace: Towards a Systematic, Global and Innovative Evaluation of the Environmental Impact of Space Activities for a Safe and Sustainable Space Environment 94
Properties of the high burnup structure in nuclear light water reactor fuel 94
Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant 94
Incorporation and verification of models and properties in fuel performance codes 94
A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools 91
IAEA FUMAC BENCHMARK ON THE HALDEN, STUDISVIK AND QUENCH-L1 LOCA TESTS 91
Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations 91
Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions 89
Report describing the irradiation experiments selected for the assessment of fuel performance codes 80
Spaceship Earth. Space-Driven Technologies and Systems for Sustainability on Ground 78
Modeling Fission Gas Release and Bubble Evolution in UO2 for Engineering Fuel Rod Analysis 78
Results of the applicative benchmark between TRANSURANUS and GERMINAL on the ASTRID case study 75
Isotropic softening model for fuel cracking in BISON 72
Microhardness and Young's modulus of high burn-up UO2 fuel 71
An effective numerical algorithm for intra-granular fission gas release during non-equilibrium trapping and resolution 71
Review of available models and progress on the sub-models dealing with the intra- and intergranular inert gas behaviour 68
Final report on rod cladding failure during SGTR 63
Synthesis of the inert gas behaviour models developed in INSPYRE 59
Fuel performance simulations of ESNII prototypes: Results on the MYRRHA case study 58
Modelling of Burst Release in Oxide Fuel and Application to the Transuranus Code 57
Modelling of the Behaviour of Inert Gases In Oxide and Mixed Oxide Nuclear Fuel under Design Basis Accident Conditions 52
Advancement in FGR modeling for transient analysis of FR fuel 51
A Physics-Based Description of Inter-Granular Helium Behaviour in SCIANTIX for Application in Fuel Performance Codes 51
Modelling Fission Gas Behaviour with the BISON Fuel Performance Code 46
Fuel Modelling in Accident Conditions (FUMAC) 46
Towards a physics-based description of intra-granular helium behaviour in oxide fuel for application in fuel performance codes 43
Three-dimensional reconstruction from experimental two-dimensional images: Application to irradiated metallic fuel 43
Extension and application of the TRANSURANUS code to the normal operating conditions of the MYRRHA reactor 42
Development of best estimate numerical tools for LFR design and safety analysis 41
3D reconstruction of two-phase random heterogeneous material from 2D sections: An approach via genetic algorithms 41
Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation 40
Development of best estimate numerical tools for LFR design and safety analysis 39
A Continuum Dislocation Dynamics Crystal Plasticity Approach to Irradiated BCC α-Iron 38
Modeling LOCA behavior with the BISON fuel performance code 37
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications 37
Fuel pin behaviour under irradiation with high Pu content: Benchmark exercise 36
A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U,Pu)O2 for fast reactors 36
Modeling high burnup structure in oxide fuels for application to fuel performance codes. Part II: Porosity evolution 36
Synthesis of INSPYRE results 35
Description of new meso-scale models and their implementation in fuel performance codes 34
Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients 34
Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions 33
SCIANTIX: A new meso-scale module enhancing fuel performance simulations 33
Modeling and Analysis of Nuclear Fuel Pin Behavior for Innovative Lead Cooled FBR 31
Modelling and Assessment of Inert Gas Behaviour in UO2 Nuclear Fuel for Transient Analysis 31
Results of the benchmark between pre- and post-INSPYRE code versions on selected experimental cases 30
Synthesis of the presentation of INSPYRE results to the User Group 30
Modelling of thermal conductivity and melting behaviour of minor actinide-MOX fuels and assessment against experimental and molecular dynamics data 30
Improvement of the BISON U3Si2 modeling capabilities based on multiscale developments to modeling fission gas behavior 28
Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment 28
Modelling fission gas behaviour in fast reactor (U,Pu)O2 fuel with BISON 21
Synthesis of the First User Group Meeting 21
On the use of spectral algorithms for the prediction of short-lived volatile fission product release: Methodology for bounding numerical error 21
Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part II: Coupling SCIANTIX with TRANSURANUS 20
On the intra-granular behaviour of a cocktail of inert gases in oxide nuclear fuel: Methodological recommendation for accelerated experimental investigation 19
Supporto alla progettazione del combustibile nucleare per Il reattore LFR 18
Towards multi-physics description of fuel behaviour for accidental conditions 15
Best practices and QA protocols for code development 14
Physics-based modelling and validation of inter-granular helium behaviour in SCIANTIX 14
Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part I: SCIANTIX 12
The SCIANTIX code for fission gas behaviour: Status, upgrades, separate-effect validation, and future developments 11
Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment 11
Third Yearly Activity Report 10
Towards simulations of fuel rod behaviour during severe accidents by coupling TRANSURANUS with SCIANTIX and MFPR-F 9
A modelling methodology for the description of helium behaviour accounting for the grain-size distribution 8
A reduced order model for fission gas diffusion in columnar grains 8
Analysis of the performance of driver MOX fuel in the MYRRHA reactor under Beam Power Jump transient irradiation conditions 5
A surrogate model for the helium production rate in fast reactor MOX fuels 4
Towards modelling defective fuel rods in TRANSURANUS: Benchmark and assessment of gaseous and volatile radioactive fission product release 4
Performance analysis and helium behaviour of Am-bearing fuel pins for irradiation in the MYRRHA reactor 2
Critical assessment of the pore size distribution in the rim region of high burnup UO2 fuels 2
Totale 3.989
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Categoria #
all - tutte 16.490
article - articoli 10.384
book - libri 0
conference - conferenze 2.198
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 136
Totale 29.208
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/2020441 0 0 0 37 52 64 97 41 43 38 41 28
2020/2021442 28 20 35 22 16 16 20 41 34 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
2024/2025158 57 44 52 5 0 0 0 0 0 0 0 0
Totale 3.989