BORTOT, SARA
 Distribuzione geografica
Continente #
NA - Nord America 694
EU - Europa 231
AS - Asia 56
AF - Africa 1
Totale 982
Nazione #
US - Stati Uniti d'America 681
UA - Ucraina 57
IT - Italia 34
AT - Austria 30
SE - Svezia 24
DE - Germania 22
FI - Finlandia 21
CN - Cina 20
VN - Vietnam 16
ES - Italia 15
JO - Giordania 15
CA - Canada 13
GB - Regno Unito 9
FR - Francia 7
IE - Irlanda 7
IN - India 4
BE - Belgio 3
RU - Federazione Russa 2
JP - Giappone 1
MU - Mauritius 1
Totale 982
Città #
Woodbridge 112
Chandler 102
Houston 92
Fairfield 51
Ashburn 40
Wilmington 40
Ann Arbor 38
Jacksonville 33
Vienna 30
Seattle 23
Cambridge 21
Amman 15
Lawrence 15
Málaga 15
Ottawa 13
Medford 12
Beijing 8
Des Moines 8
Dong Ket 7
Dublin 7
Shanghai 7
Helsinki 6
Dearborn 4
Brussels 3
Changsha 3
Milan 3
Princeton 3
Lanzhou 2
London 2
Mountain View 2
Redwood City 2
San Diego 2
Verona 2
Atlanta 1
Boardman 1
Edinburgh 1
Ercolano 1
Gorla Minore 1
Gunzenhausen 1
Marseille 1
Moscow 1
Norwalk 1
Portland 1
Rome 1
St Petersburg 1
Stockholm 1
Tokyo 1
Totale 737
Nome #
Dynamic performance assessment of MOX and metallic fuel core options for a Gen-IV LFR demonstrator 130
Feasibility Studies and Scope Analyses for a SUPERSTAR DemonstratorNeutronics Design 116
Analytical models for a small LFR core dynamics studies 93
A Simplified Model for a Preliminary Study of the Dynamic Behaviour of a Small GEN IV LFR DEMO 89
Preliminary Core Characterization of a Generation IV Lead Fast Reactor DEMO: Goals, Design Rationales and Options 76
Impact of linear and non-linear kinetics models on a small LFR core dynamics 61
Deterministic and Stochastic Approach for a Void Reactivity Effect Evaluation: application to a Generation IV Lead Fast Reactor (LFR) 60
Safety Issues Affecting the Feasibility of an Early High-Flux LFR Technology Demonstrator 53
Approach to a Preliminary Core Characterization of a Generation IV Lead-cooled Fast Reactor Demonstration Project: Goals and Rationales 52
Preliminary Core Characterization for an ELSY-Oriented Demonstrative Reactor 51
Transient Evaluation of a GEN IV LFR Demonstration Plant througha Lumped Parameters Analysis of Coupled Kinetics and Thermal-Hydraulics 49
Modeling Approaches for Dynamic Analyses of Innovative SMRs Compact Steam Generators 49
Feasibility studies and scope analysis for a SUPERSTAR Demonstrator neutronics design 48
Feedback Coefficients Evaluation for an Advanced LFR Demonstrative Reactor 44
On the Application of Neutron Kinetics Models for a Small LFR Core Transient Analysis 36
Totale 1.007
Categoria #
all - tutte 2.805
article - articoli 1.081
book - libri 0
conference - conferenze 1.724
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 5.610


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2018/201951 0 0 0 0 0 0 0 0 0 0 25 26
2019/2020202 10 4 4 10 20 50 25 12 27 9 25 6
2020/2021137 15 10 20 13 9 5 13 14 7 6 6 19
2021/202284 4 19 3 0 6 2 5 7 6 2 6 24
2022/2023211 15 13 11 24 22 30 0 15 47 19 12 3
2023/202453 8 13 1 3 4 2 0 18 0 2 2 0
Totale 1.007