MAGNI, ALESSIO
 Distribuzione geografica
Continente #
NA - Nord America 243
EU - Europa 149
AS - Asia 42
AF - Africa 3
OC - Oceania 1
Totale 438
Nazione #
US - Stati Uniti d'America 240
IT - Italia 59
FR - Francia 37
CN - Cina 11
GB - Regno Unito 11
UA - Ucraina 11
AT - Austria 10
CH - Svizzera 7
IR - Iran 7
KR - Corea 6
JP - Giappone 5
CZ - Repubblica Ceca 4
HK - Hong Kong 4
IN - India 4
CA - Canada 3
GR - Grecia 3
RU - Federazione Russa 3
ZA - Sudafrica 3
AE - Emirati Arabi Uniti 2
NL - Olanda 2
TR - Turchia 2
AU - Australia 1
DE - Germania 1
IQ - Iraq 1
RO - Romania 1
Totale 438
Città #
Santa Cruz 32
Fairfield 23
Buffalo 15
Milan 15
Houston 14
Gif-sur-yvette 9
Seattle 9
Ashburn 8
Vienna 8
Cambridge 7
Woodbridge 7
Guangzhou 5
San Diego 5
Abbiategrasso 4
Ann Arbor 4
Council Bluffs 4
Lausanne 4
Tulsa 4
Bengaluru 3
Central District 3
Chicago 3
London 3
Mountain View 3
Saint Petersburg 3
Villeneuve-Loubet 3
Wilmington 3
Abu Dhabi 2
Bitonto 2
Blue Bell 2
Chabahar 2
Clearwater 2
Fatih 2
Henderson 2
Muizenberg 2
Ottawa 2
Provo 2
Riva 2
Saint-Maximin-la-Sainte-Baume 2
San Giorgio A Cremano 2
Shanghai 2
Yellow Springs 2
Aix-en-Provence 1
Avignon 1
Bardoli 1
Birmingham 1
Bucharest 1
Changchun 1
Clarksville 1
Duhok 1
Easton 1
Falls Church 1
Gavirate 1
Gif-sur-Yvette 1
Gold Coast 1
Groningen 1
Hefei 1
Huntsville 1
Idaho Falls 1
Lake Forest 1
Las Vegas 1
Los Alamos 1
Marseille 1
Nanterre 1
Neuchatel 1
New York 1
Paris 1
Peccioli 1
Peyrolles-en-Provence 1
Phoenix 1
Reading 1
Rochegude 1
Roquemaure 1
Saint-laurent-du-var 1
Santa Clara 1
Scottsdale 1
Scranton 1
Seoul 1
Shenyang 1
Silverton 1
Sion 1
Solothurn 1
Terracina 1
Tokyo 1
Toronto 1
Trieste 1
University Park 1
Vedelago 1
Villeneuve 1
Wuhan 1
Totale 279
Nome #
A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools, file e0c31c0c-1c20-4599-e053-1705fe0aef77 118
Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients, file e0c31c10-072f-4599-e053-1705fe0aef77 51
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications, file e0c31c0f-a502-4599-e053-1705fe0aef77 40
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 37
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 35
Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment, file e0c31c11-66e1-4599-e053-1705fe0aef77 33
Incorporation and verification of models and properties in fuel performance codes, file e0c31c11-3282-4599-e053-1705fe0aef77 26
Report on the improved models of melting temperature and thermal conductivity for MOX fuels and JOG, file e0c31c11-0a0c-4599-e053-1705fe0aef77 23
Results of the applicative benchmark between TRANSURANUS and GERMINAL on the ASTRID case study, file e0c31c11-5faa-4599-e053-1705fe0aef77 18
Synthesis of the inert gas behaviour models developed in INSPYRE, file e0c31c11-000c-4599-e053-1705fe0aef77 15
Improved models of melting temperature and thermal conductivity for mixed oxide fuels doped with low minor actinide contents, file f4ebaf42-d062-4a67-8c8f-8800dc2da342 15
Report describing the irradiation experiments selected for the assessment of fuel performance codes, file e0c31c11-43a5-4599-e053-1705fe0aef77 12
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 10
Extension and application of the TRANSURANUS code to the normal operating conditions of the MYRRHA reactor, file e0c31c11-f94e-4599-e053-1705fe0aef77 10
A Physics-Based Description of Inter-Granular Helium Behaviour in SCIANTIX for Application in Fuel Performance Codes, file e0c31c12-890d-4599-e053-1705fe0aef77 8
Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part I: SCIANTIX, file 349fe6f6-fa64-44f8-aec3-7a8681055a88 4
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 2
Physics-based modelling and validation of inter-granular helium behaviour in SCIANTIX, file 51c36818-c26d-4300-b58e-37b5bc8c7a52 2
Modeling Fission Gas Release and Bubble Evolution in UO2 for Engineering Fuel Rod Analysis, file e0c31c0c-de4b-4599-e053-1705fe0aef77 1
The TRANSURANUS fuel performance code, file e0c31c10-a3e8-4599-e053-1705fe0aef77 1
Totale 461
Categoria #
all - tutte 707
article - articoli 483
book - libri 0
conference - conferenze 14
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 1
Totale 1205


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2017/20182 0000 00 00 2000
2018/201919 0000 00 00 4465
2019/202032 4222 33 33 3133
2020/202164 1412 32 34 98243
2021/2022216 324116 2919 813 2564626
2022/2023128 1684829 207 00 0000
Totale 461