PIZZOCRI, DAVIDE
 Distribuzione geografica
Continente #
EU - Europa 1.815
NA - Nord America 1.391
AS - Asia 527
AF - Africa 27
SA - Sud America 15
OC - Oceania 12
Continente sconosciuto - Info sul continente non disponibili 1
Totale 3.788
Nazione #
US - Stati Uniti d'America 1.348
IT - Italia 809
FR - Francia 298
CN - Cina 164
DE - Germania 98
RU - Federazione Russa 95
GB - Regno Unito 91
KR - Corea 86
IR - Iran 70
JP - Giappone 51
AT - Austria 45
CZ - Repubblica Ceca 43
UA - Ucraina 43
CA - Canada 41
RO - Romania 41
CH - Svizzera 39
IN - India 35
HU - Ungheria 34
NL - Olanda 33
SE - Svezia 31
SG - Singapore 30
HK - Hong Kong 29
HR - Croazia 24
VN - Vietnam 19
BE - Belgio 18
FI - Finlandia 17
ES - Italia 13
BR - Brasile 12
ZA - Sudafrica 12
AU - Australia 11
IE - Irlanda 11
LT - Lituania 10
AE - Emirati Arabi Uniti 9
TW - Taiwan 8
GR - Grecia 6
TR - Turchia 6
DZ - Algeria 5
EG - Egitto 5
ID - Indonesia 5
SK - Slovacchia (Repubblica Slovacca) 5
LU - Lussemburgo 3
SI - Slovenia 3
AR - Argentina 2
BD - Bangladesh 2
CY - Cipro 2
DK - Danimarca 2
EE - Estonia 2
MY - Malesia 2
PH - Filippine 2
PK - Pakistan 2
A2 - ???statistics.table.value.countryCode.A2??? 1
AF - Afghanistan, Repubblica islamica di 1
CL - Cile 1
GH - Ghana 1
HN - Honduras 1
IL - Israele 1
IQ - Iraq 1
KE - Kenya 1
LB - Libano 1
LY - Libia 1
MD - Moldavia 1
MX - Messico 1
NC - Nuova Caledonia 1
NG - Nigeria 1
SA - Arabia Saudita 1
SD - Sudan 1
Totale 3.788
Città #
Milan 236
Fairfield 106
Ashburn 97
Santa Cruz 92
Houston 79
Buffalo 63
Seattle 45
Cambridge 40
Vienna 38
Ann Arbor 36
Budapest 32
Woodbridge 29
Paris 28
Bologna 27
Tortona 26
Los Angeles 25
Rome 25
Turin 25
Wilmington 25
Gif-sur-yvette 23
Chicago 22
Moscow 22
Zagreb 22
Shanghai 21
Bucharest 20
Tokyo 20
Beijing 19
Council Bluffs 19
Redmond 19
Boardman 18
London 17
San Diego 17
Aix-en-Provence 16
Fleming Island 16
Abbiategrasso 15
Idaho Falls 15
Guangzhou 14
Marseille 14
Lausanne 13
New York 13
Stockholm 13
Karlsruhe 12
Dublin 11
Mountain View 11
Villeneuve 11
Cernusco sul Naviglio 10
Richmond 10
Shenzhen 10
St Petersburg 10
Trieste 10
Amsterdam 9
Atlanta 9
Bergamo 9
Dong Ket 9
Las Vegas 9
Madison 9
Potenza 9
Prague 9
Toronto 9
Brooklyn 8
Clearwater 8
Grenoble 8
Monza 8
Muizenberg 8
Ottawa 8
Torino 8
Como 7
Fremont 7
Genoa 7
Kyiv 7
Manchester 7
Monroeville 7
Ollieres 7
Bengaluru 6
Cedar Knolls 6
Cortenuova 6
Dallas 6
Harbin 6
Helsinki 6
Lancaster 6
Los Alamos 6
Mumbai 6
Nanchang 6
Nürnberg 6
Provo 6
Rousset-les-Vignes 6
Tulsa 6
Wuhan 6
Xi'an 6
Albuquerque 5
Almè 5
Bari 5
Central District 5
Chengdu 5
Gainesville 5
Hamilton 5
Hangzhou 5
Hillsboro 5
Kingston 5
Lake Forest 5
Totale 1.894
Nome #
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor, file e0c31c0d-8364-4599-e053-1705fe0aef77 816
Properties of the high burnup structure in nuclear light water reactor fuel, file e0c31c0c-258e-4599-e053-1705fe0aef77 471
Final report on rod cladding failure during SGTR, file eedd6d35-ee8e-41eb-a9f7-a64f0d904d50 149
SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes, file e0c31c0f-4faa-4599-e053-1705fe0aef77 146
A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools, file e0c31c0c-1c20-4599-e053-1705fe0aef77 134
Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS, file e0c31c0f-3db2-4599-e053-1705fe0aef77 123
Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation, file e0c31c0f-aa25-4599-e053-1705fe0aef77 122
A Continuum Dislocation Dynamics Crystal Plasticity Approach to Irradiated BCC α-Iron, file e0c31c11-c717-4599-e053-1705fe0aef77 120
Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations, file e0c31c0b-9f7d-4599-e053-1705fe0aef77 119
Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant, file e0c31c0c-8282-4599-e053-1705fe0aef77 109
Microhardness and Young's modulus of high burn-up UO2 fuel, file e0c31c09-bec0-4599-e053-1705fe0aef77 103
Spaceship Earth. Space-driven technologies and systems for sustainability on ground, file e0c31c08-6086-4599-e053-1705fe0aef77 95
Development of best estimate numerical tools for LFR design and safety analysis, file e0c31c11-2334-4599-e053-1705fe0aef77 85
Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions, file e0c31c12-7f7d-4599-e053-1705fe0aef77 84
Incorporation and verification of models and properties in fuel performance codes, file e0c31c11-3282-4599-e053-1705fe0aef77 74
Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients, file e0c31c10-072f-4599-e053-1705fe0aef77 72
IAEA FUMAC BENCHMARK ON THE HALDEN, STUDISVIK AND QUENCH-L1 LOCA TESTS, file e0c31c0d-3713-4599-e053-1705fe0aef77 65
Towards a physics-based description of intra-granular helium behaviour in oxide fuel for application in fuel performance codes, file e0c31c10-d8a9-4599-e053-1705fe0aef77 63
Report describing the irradiation experiments selected for the assessment of fuel performance codes, file e0c31c11-43a5-4599-e053-1705fe0aef77 60
Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment, file e0c31c11-66e1-4599-e053-1705fe0aef77 57
Review of available models and progress on the sub-models dealing with the intra- and intergranular inert gas behaviour, file e0c31c10-f6f8-4599-e053-1705fe0aef77 56
SCIANTIX: A new meso-scale module enhancing fuel performance simulations, file e0c31c0f-08d5-4599-e053-1705fe0aef77 53
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications, file e0c31c0f-a502-4599-e053-1705fe0aef77 53
3D reconstruction of two-phase random heterogeneous material from 2D sections: An approach via genetic algorithms, file e0c31c11-c716-4599-e053-1705fe0aef77 48
A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U,Pu)O2 for fast reactors, file e0c31c11-730b-4599-e053-1705fe0aef77 46
Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part I: SCIANTIX, file 349fe6f6-fa64-44f8-aec3-7a8681055a88 38
Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part II: Coupling SCIANTIX with TRANSURANUS, file d13d261f-9f9a-4562-8111-6b2968efa829 38
Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions, file 4a4c0296-13dc-4e2c-b862-41e38364b1b6 34
Synthesis of INSPYRE results, file d48a7793-5d73-4d02-95c2-ff437496291b 30
Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment, file e7e10bd5-806d-4a25-bb59-2875e7d449d7 30
Modeling high burnup structure in oxide fuels for application to fuel performance codes. Part II: Porosity evolution, file e0c31c12-87ff-4599-e053-1705fe0aef77 27
On the intra-granular behaviour of a cocktail of inert gases in oxide nuclear fuel: Methodological recommendation for accelerated experimental investigation, file e0c31c12-e999-4599-e053-1705fe0aef77 27
Synthesis of the presentation of INSPYRE results to the User Group, file 9a0544ca-5818-490a-85d3-5a4c8b737046 26
Results of the applicative benchmark between TRANSURANUS and GERMINAL on the ASTRID case study, file e0c31c11-5faa-4599-e053-1705fe0aef77 26
Synthesis of the inert gas behaviour models developed in INSPYRE, file e0c31c11-000c-4599-e053-1705fe0aef77 24
Extension and application of the TRANSURANUS code to the normal operating conditions of the MYRRHA reactor, file e0c31c11-f94e-4599-e053-1705fe0aef77 24
Modelling of thermal conductivity and melting behaviour of minor actinide-MOX fuels and assessment against experimental and molecular dynamics data, file e0c31c11-831e-4599-e053-1705fe0aef77 21
Fuel performance simulations of ESNII prototypes: Results on the MYRRHA case study, file 67e60494-3ef6-499b-8963-3f77d2331374 20
A Physics-Based Description of Inter-Granular Helium Behaviour in SCIANTIX for Application in Fuel Performance Codes, file e0c31c12-890d-4599-e053-1705fe0aef77 18
Physics-based modelling and validation of inter-granular helium behaviour in SCIANTIX, file 51c36818-c26d-4300-b58e-37b5bc8c7a52 16
On the use of spectral algorithms for the prediction of short-lived volatile fission product release: Methodology for bounding numerical error, file e0c31c12-4a03-4599-e053-1705fe0aef77 16
Results of the benchmark between pre- and post-INSPYRE code versions on selected experimental cases, file fbc03e51-510d-4843-8083-35c8f07eddb4 14
Synthesis of the First User Group Meeting, file e0c31c11-000a-4599-e053-1705fe0aef77 13
Description of new meso-scale models and their implementation in fuel performance codes, file f6e82746-a87a-47b7-83bf-d9526b4bc972 11
Third Yearly Activity Report, file 0c5e3fa9-5fbd-42e1-9cb8-2743db035309 9
Modelling of the Behaviour of Inert Gases In Oxide and Mixed Oxide Nuclear Fuel under Design Basis Accident Conditions, file e0c31c0f-0a02-4599-e053-1705fe0aef77 9
Towards multi-physics description of fuel behaviour for accidental conditions, file 0c5511c1-ac74-4094-926f-0b879e7fbf96 5
A surrogate model for the helium production rate in fast reactor MOX fuels, file 1888f666-30df-4998-9078-06f8d76bfe67 4
A modelling methodology for the description of helium behaviour accounting for the grain-size distribution, file 24714dd1-5353-40ed-89b1-d8ad52be28bc 4
Towards simulations of fuel rod behaviour during severe accidents by coupling TRANSURANUS with SCIANTIX and MFPR-F, file a6d0aca8-8468-4fbb-bb76-009d1762af4e 4
Best practices and QA protocols for code development, file c4e790d9-b3ed-40f8-999d-9fa78dd49637 4
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor, file e0c31c08-1def-4599-e053-1705fe0aef77 4
Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS, file e0c31c0a-3b50-4599-e053-1705fe0aef77 4
Analysis of the performance of driver MOX fuel in the MYRRHA reactor under Beam Power Jump transient irradiation conditions, file 7fae6c01-455c-469a-9376-53438664a5ba 3
The SCIANTIX code for fission gas behaviour: Status, upgrades, separate-effect validation, and future developments, file c23885ec-ea54-4582-8235-430650f27c8b 3
A reduced order model for fission gas diffusion in columnar grains, file c302733e-ec86-4a6f-b53d-00bf256fb749 3
Spaceship Earth. Space-driven technologies and systems for sustainability on ground, file e0c31c08-5d85-4599-e053-1705fe0aef77 3
An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions, file e0c31c0a-dfdd-4599-e053-1705fe0aef77 3
Modelling of Transient Fission Gas Behaviour in Oxide Fuel and Application to the BISON Code, file e0c31c07-be9f-4599-e053-1705fe0aef77 2
Spaceship Earth. Space-Driven Technologies and Systems for Sustainability on Ground, file e0c31c08-254c-4599-e053-1705fe0aef77 2
A semi-empirical model for the formation and depletion of the high burnup structure in UO2, file e0c31c0a-4990-4599-e053-1705fe0aef77 2
Advancement in FGR modeling for transient analysis of FR fuel, file e0c31c0b-6baa-4599-e053-1705fe0aef77 2
Modelling Fission Gas Behaviour with the BISON Fuel Performance Code, file e0c31c0c-054d-4599-e053-1705fe0aef77 2
An effective numerical algorithm for intra-granular fission gas release during non-equilibrium trapping and resolution, file e0c31c0c-8549-4599-e053-1705fe0aef77 2
Isotropic softening model for fuel cracking in BISON, file e0c31c0c-d421-4599-e053-1705fe0aef77 2
Three-dimensional reconstruction from experimental two-dimensional images: Application to irradiated metallic fuel, file e0c31c10-96ba-4599-e053-1705fe0aef77 2
Modelling fission gas behaviour in fast reactor (U,Pu)O2 fuel with BISON, file e0c31c10-e626-4599-e053-1705fe0aef77 2
Improvement of the BISON U3Si2 modeling capabilities based on multiscale developments to modeling fission gas behavior, file e0c31c11-9d75-4599-e053-1705fe0aef77 2
Greenspace: Towards a Systematic, Global and Innovative Evaluation of the Environmental Impact of Space Activities for a Safe and Sustainable Space Environment, file e0c31c08-254b-4599-e053-1705fe0aef77 1
Modelling of Burst Release in Oxide Fuel and Application to the Transuranus Code, file e0c31c0a-6bbb-4599-e053-1705fe0aef77 1
Modeling Fission Gas Release and Bubble Evolution in UO2 for Engineering Fuel Rod Analysis, file e0c31c0c-de4b-4599-e053-1705fe0aef77 1
Modelling and Assessment of Inert Gas Behaviour in UO2 Nuclear Fuel for Transient Analysis, file e0c31c0d-38d9-4599-e053-1705fe0aef77 1
Performance analysis and helium behaviour of Am-bearing fuel pins for irradiation in the MYRRHA reactor, file f6def39d-fa91-41ac-90db-a0f8164f4e59 1
Totale 3.863
Categoria #
all - tutte 9.060
article - articoli 7.184
book - libri 0
conference - conferenze 499
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 16.743


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2018/201996 0 0 0 0 0 0 0 0 10 19 35 32
2019/2020270 22 13 10 22 24 20 26 24 25 33 24 27
2020/2021484 22 25 29 28 31 31 29 37 66 49 67 70
2021/2022953 43 72 71 119 106 66 58 60 70 35 168 85
2022/20231.105 32 41 151 106 91 91 114 96 92 101 110 80
2023/2024926 86 81 94 91 95 68 172 131 108 0 0 0
Totale 3.863