ZULLO, GIOVANNI
 Distribuzione geografica
Continente #
EU - Europa 99
NA - Nord America 36
AS - Asia 31
AF - Africa 4
SA - Sud America 2
Totale 172
Nazione #
IT - Italia 58
US - Stati Uniti d'America 36
CN - Cina 14
SG - Singapore 12
ES - Italia 9
GB - Regno Unito 7
FI - Finlandia 6
IE - Irlanda 6
CH - Svizzera 3
JO - Giordania 3
RU - Federazione Russa 3
BE - Belgio 2
BR - Brasile 2
CI - Costa d'Avorio 2
HK - Hong Kong 2
AT - Austria 1
DE - Germania 1
FR - Francia 1
HR - Croazia 1
NG - Nigeria 1
NL - Olanda 1
ZA - Sudafrica 1
Totale 172
Città #
Milan 24
Singapore 9
Dublin 6
Málaga 6
Lancaster 5
Helsinki 4
Amman 3
Hillsboro 3
Madrid 3
Zurich 3
Abidjan 2
Brussels 2
Cesano Boscone 2
Columbus 2
Cortenuova 2
Genoa 2
Lappeenranta 2
New York 2
Tortona 2
Wanchai 2
Altamura 1
Americana 1
Amsterdam 1
Ashburn 1
Ceriano Laghetto 1
Chicago 1
Chiswick 1
Florence 1
Grenoble 1
Johannesburg 1
Kilburn 1
Lagos 1
Lawrence 1
Medford 1
North Bergen 1
Redmond 1
Rome 1
St Petersburg 1
São Paulo 1
Vienna 1
Woodbridge 1
Zagreb 1
Totale 108
Nome #
Final report on rod cladding failure during SGTR 58
Description of new meso-scale models and their implementation in fuel performance codes 31
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
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
The SCIANTIX code for fission gas behaviour: Status, upgrades, separate-effect validation, and future developments 9
Towards simulations of fuel rod behaviour during severe accidents by coupling TRANSURANUS with SCIANTIX and MFPR-F 8
A reduced order model for fission gas diffusion in columnar grains 5
A surrogate model for the helium production rate in fast reactor MOX fuels 3
Analysis of the performance of driver MOX fuel in the MYRRHA reactor under Beam Power Jump transient irradiation conditions 3
Towards modelling defective fuel rods in TRANSURANUS: Benchmark and assessment of gaseous and volatile radioactive fission product release 2
Performance analysis and helium behaviour of Am-bearing fuel pins for irradiation in the MYRRHA reactor 2
Totale 187
Categoria #
all - tutte 1.451
article - articoli 1.148
book - libri 0
conference - conferenze 0
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 2.599


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2021/20228 0 0 0 0 0 0 0 0 0 0 7 1
2022/202361 1 1 0 0 5 0 0 0 24 14 10 6
2023/2024109 3 10 7 4 3 5 17 10 7 6 20 17
2024/20259 9 0 0 0 0 0 0 0 0 0 0 0
Totale 187