ZULLO, GIOVANNI
 Distribuzione geografica
Continente #
EU - Europa 141
NA - Nord America 127
AS - Asia 68
AF - Africa 9
SA - Sud America 2
Totale 347
Nazione #
US - Stati Uniti d'America 127
IT - Italia 82
SG - Singapore 29
CN - Cina 21
ID - Indonesia 12
FI - Finlandia 11
ES - Italia 9
FR - Francia 7
GB - Regno Unito 7
IE - Irlanda 6
NL - Olanda 6
BJ - Benin 4
CH - Svizzera 3
JO - Giordania 3
RU - Federazione Russa 3
BE - Belgio 2
BR - Brasile 2
CI - Costa d'Avorio 2
DE - Germania 2
HK - Hong Kong 2
NG - Nigeria 2
AT - Austria 1
HR - Croazia 1
PH - Filippine 1
PL - Polonia 1
ZA - Sudafrica 1
Totale 347
Città #
Santa Clara 68
Milan 35
Singapore 25
Boardman 13
Jakarta 12
Lappeenranta 7
Dublin 6
Málaga 6
Amsterdam 5
Lancaster 5
Paris 5
Cotonou 4
Helsinki 4
Hillsboro 4
Amman 3
Ashburn 3
Madrid 3
New York 3
Zurich 3
Abidjan 2
Brussels 2
Cabiate 2
Cesano Boscone 2
Columbus 2
Cortenuova 2
Genoa 2
Grenoble 2
Rome 2
Seattle 2
Tortona 2
Wanchai 2
Altamura 1
Americana 1
Baoding 1
Ceriano Laghetto 1
Chicago 1
Chiswick 1
Florence 1
Iesi 1
Johannesburg 1
Kilburn 1
Lagos 1
Lawrence 1
Linkenheim-Hochstetten 1
Manila 1
Medford 1
North Bergen 1
Paderno Dugnano 1
Pieve Emanuele 1
Redmond 1
San Jose 1
St Petersburg 1
São Paulo 1
Vienna 1
Warsaw 1
Woodbridge 1
Zagreb 1
Totale 264
Nome #
Final report on rod cladding failure during SGTR 70
Description of new meso-scale models and their implementation in fuel performance codes 53
On the use of spectral algorithms for the prediction of short-lived volatile fission product release: Methodology for bounding numerical error 29
Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part II: Coupling SCIANTIX with TRANSURANUS 28
Physics-based modelling and validation of inter-granular helium behaviour in SCIANTIX 22
Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part I: SCIANTIX 20
The SCIANTIX code for fission gas behaviour: Status, upgrades, separate-effect validation, and future developments 19
Towards modelling defective fuel rods in TRANSURANUS: Benchmark and assessment of gaseous and volatile radioactive fission product release 19
A reduced order model for fission gas diffusion in columnar grains 18
Towards simulations of fuel rod behaviour during severe accidents by coupling TRANSURANUS with SCIANTIX and MFPR-F 16
Performance analysis and helium behaviour of Am-bearing fuel pins for irradiation in the MYRRHA reactor 15
A surrogate model for the helium production rate in fast reactor MOX fuels 13
Analysis of the performance of driver MOX fuel in the MYRRHA reactor under Beam Power Jump transient irradiation conditions 13
Status and Planned Activities for the SCIANTIX Code Application to High Burnup Fuels 7
On the definition of the escape rate coefficient 6
Consideration of Cr-doped UO2 fuel performance for a Fluoride-Cooled High Temperature Reactor concept 5
Two-phase modelling for fission gas sweeping in restructuring nuclear oxide fuel 5
Integral-scale validation of the SCIANTIX code for Light Water Reactor fuel rods 5
Chromia-doped UO2 fuel: An engineering model for chromium solubility and fission gas diffusivity 5
Totale 368
Categoria #
all - tutte 2.403
article - articoli 1.920
book - libri 0
conference - conferenze 35
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 4.358


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
2024/2025190 12 4 13 16 66 79 0 0 0 0 0 0
Totale 368