PIZZOCRI, DAVIDE
 Distribuzione geografica
Continente #
NA - Nord America 2.019
EU - Europa 1.201
AS - Asia 285
AF - Africa 34
SA - Sud America 12
OC - Oceania 7
Continente sconosciuto - Info sul continente non disponibili 2
Totale 3.560
Nazione #
US - Stati Uniti d'America 1.976
IT - Italia 450
FR - Francia 108
FI - Finlandia 71
BE - Belgio 69
GB - Regno Unito 69
CN - Cina 65
JO - Giordania 63
AT - Austria 62
IE - Irlanda 62
ES - Italia 58
DE - Germania 55
VN - Vietnam 52
SE - Svezia 51
CA - Canada 32
UA - Ucraina 30
CH - Svizzera 24
HU - Ungheria 24
JP - Giappone 23
HK - Hong Kong 18
IR - Iran 17
NL - Olanda 17
ZA - Sudafrica 16
KR - Corea 14
MX - Messico 10
RU - Federazione Russa 10
RO - Romania 9
DK - Danimarca 7
IN - India 7
AU - Australia 6
CI - Costa d'Avorio 6
CL - Cile 6
GR - Grecia 6
EG - Egitto 5
SG - Singapore 5
TR - Turchia 5
BR - Brasile 4
PT - Portogallo 4
LI - Liechtenstein 3
NG - Nigeria 3
NO - Norvegia 3
PK - Pakistan 3
SA - Arabia Saudita 3
AE - Emirati Arabi Uniti 2
BD - Bangladesh 2
CO - Colombia 2
EU - Europa 2
MY - Malesia 2
PL - Polonia 2
TW - Taiwan 2
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 3.560
Città #
Chandler 255
Fairfield 246
Milan 172
Ashburn 130
Seattle 109
Wilmington 105
Woodbridge 104
Houston 93
Cambridge 81
Ann Arbor 73
Amman 63
Dublin 60
Vienna 59
Brussels 58
Helsinki 56
Málaga 53
Lawrence 51
Medford 47
Dearborn 35
New York 33
Redwood City 31
Redmond 29
Ottawa 26
Tortona 24
Budapest 23
Rome 20
Beijing 19
San Diego 18
Gif-sur-yvette 16
Johannesburg 16
Los Angeles 16
London 14
Norwalk 14
Columbus 12
Dong Ket 12
Tokyo 11
Bologna 10
Amsterdam 9
Gainesville 9
Mountain View 9
Princeton 9
Aix-en-Provence 8
College Station 8
Edinburgh 8
Hefei 8
Lausanne 8
Paris 8
Berlin 7
Idaho Falls 7
Munich 7
Abidjan 6
Bordeaux 6
Chicago 6
Concepción 6
Copenhagen 6
Lancaster 6
Nanterre 6
Stockholm 6
Boydton 5
Central 5
Des Moines 5
Jacksonville 5
Kyiv 5
Marseille 5
Mumbai 5
San Jose 5
Seoul 5
Torino 5
Zurich 5
Bovisio Masciago 4
Buc 4
Bucharest 4
Cortenuova 4
Guangzhou 4
Hong Kong 4
Le Pecq 4
Phoenix 4
Rousset-les-Vignes 4
Shanghai 4
Singapore 4
Turin 4
Vinon-sur-Verdon 4
Alexandria 3
Altamura 3
Bareggio 3
Chabahar 3
Ciampino 3
Cleator Moor 3
Como 3
Fremont 3
Garching 3
Genoa 3
Grenoble 3
Groningen 3
Islamabad 3
Lemont 3
Madison 3
Melbourne 3
Miami 3
Naucalpan 3
Totale 2.508
Nome #
SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes 152
Spaceship Earth. Space-driven technologies and systems for sustainability on ground 124
An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions 111
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor 109
Modelling of Transient Fission Gas Behaviour in Oxide Fuel and Application to the BISON Code 106
Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS 103
PolyPole-1: An accurate numerical algorithm for intra-granular fission gas release 100
A semi-empirical model for the formation and depletion of the high burnup structure in UO2 99
Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant 94
Greenspace: Towards a Systematic, Global and Innovative Evaluation of the Environmental Impact of Space Activities for a Safe and Sustainable Space Environment 93
Incorporation and verification of models and properties in fuel performance codes 92
Properties of the high burnup structure in nuclear light water reactor fuel 91
Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations 90
A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools 88
Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions 88
Development of best estimate numerical tools for LFR design and safety analysis 83
IAEA FUMAC BENCHMARK ON THE HALDEN, STUDISVIK AND QUENCH-L1 LOCA TESTS 82
Spaceship Earth. Space-Driven Technologies and Systems for Sustainability on Ground 77
Modeling Fission Gas Release and Bubble Evolution in UO2 for Engineering Fuel Rod Analysis 74
Microhardness and Young's modulus of high burn-up UO2 fuel 71
Isotropic softening model for fuel cracking in BISON 71
An effective numerical algorithm for intra-granular fission gas release during non-equilibrium trapping and resolution 71
Results of the applicative benchmark between TRANSURANUS and GERMINAL on the ASTRID case study 70
Review of available models and progress on the sub-models dealing with the intra- and intergranular inert gas behaviour 68
Report describing the irradiation experiments selected for the assessment of fuel performance codes 62
Final report on rod cladding failure during SGTR 57
Synthesis of the inert gas behaviour models developed in INSPYRE 56
Modelling of Burst Release in Oxide Fuel and Application to the Transuranus Code 54
Modelling of the Behaviour of Inert Gases In Oxide and Mixed Oxide Nuclear Fuel under Design Basis Accident Conditions 50
Advancement in FGR modeling for transient analysis of FR fuel 49
A Physics-Based Description of Inter-Granular Helium Behaviour in SCIANTIX for Application in Fuel Performance Codes 48
Modelling Fission Gas Behaviour with the BISON Fuel Performance Code 47
Fuel performance simulations of ESNII prototypes: Results on the MYRRHA case study 43
Towards a physics-based description of intra-granular helium behaviour in oxide fuel for application in fuel performance codes 42
Extension and application of the TRANSURANUS code to the normal operating conditions of the MYRRHA reactor 42
Fuel Modelling in Accident Conditions (FUMAC) 41
Three-dimensional reconstruction from experimental two-dimensional images: Application to irradiated metallic fuel 41
Development of best estimate numerical tools for LFR design and safety analysis 41
Development of best estimate numerical tools for LFR design and safety analysis 40
A Continuum Dislocation Dynamics Crystal Plasticity Approach to Irradiated BCC α-Iron 39
Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation 38
3D reconstruction of two-phase random heterogeneous material from 2D sections: An approach via genetic algorithms 37
Modeling LOCA behavior with the BISON fuel performance code 36
A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U,Pu)O2 for fast reactors 33
Modeling high burnup structure in oxide fuels for application to fuel performance codes. Part II: Porosity evolution 33
Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients 32
SCIANTIX: A new meso-scale module enhancing fuel performance simulations 31
Results of the benchmark between pre- and post-INSPYRE code versions on selected experimental cases 30
Modelling and Assessment of Inert Gas Behaviour in UO2 Nuclear Fuel for Transient Analysis 30
Modeling and Analysis of Nuclear Fuel Pin Behavior for Innovative Lead Cooled FBR 29
Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment 28
Synthesis of INSPYRE results 27
Synthesis of the presentation of INSPYRE results to the User Group 27
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications 27
Improvement of the BISON U3Si2 modeling capabilities based on multiscale developments to modeling fission gas behavior 27
Modelling of thermal conductivity and melting behaviour of minor actinide-MOX fuels and assessment against experimental and molecular dynamics data 27
Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions 26
Fuel pin behaviour under irradiation with high Pu content: Benchmark exercise 23
Synthesis of the First User Group Meeting 20
On the use of spectral algorithms for the prediction of short-lived volatile fission product release: Methodology for bounding numerical error 20
Modelling fission gas behaviour in fast reactor (U,Pu)O2 fuel with BISON 18
On the intra-granular behaviour of a cocktail of inert gases in oxide nuclear fuel: Methodological recommendation for accelerated experimental investigation 18
Supporto alla progettazione del combustibile nucleare per Il reattore LFR 17
Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part II: Coupling SCIANTIX with TRANSURANUS 16
Description of new meso-scale models and their implementation in fuel performance codes 14
Physics-based modelling and validation of inter-granular helium behaviour in SCIANTIX 13
Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part I: SCIANTIX 12
Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment 9
Towards multi-physics description of fuel behaviour for accidental conditions 7
Best practices and QA protocols for code development 7
Third Yearly Activity Report 4
A reduced order model for fission gas diffusion in columnar grains 4
Towards simulations of fuel rod behaviour during severe accidents by coupling TRANSURANUS with SCIANTIX and MFPR-F 3
The SCIANTIX code for fission gas behaviour: Status, upgrades, separate-effect validation, and future developments 3
A modelling methodology for the description of helium behaviour accounting for the grain-size distribution 2
A surrogate model for the helium production rate in fast reactor MOX fuels 1
Critical assessment of the pore size distribution in the rim region of high burnup UO2 fuels 1
Analysis of the performance of driver MOX fuel in the MYRRHA reactor under Beam Power Jump transient irradiation conditions 1
Totale 3.690
Categoria #
all - tutte 12.521
article - articoli 8.196
book - libri 0
conference - conferenze 1.738
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 100
Totale 22.555


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2018/2019243 0 0 0 0 0 0 0 0 33 50 86 74
2019/2020510 32 31 6 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
2022/20231.062 69 58 54 73 92 109 37 78 209 106 105 72
2023/2024595 49 96 37 56 61 88 86 82 40 0 0 0
Totale 3.690