FRISONI, MANUELA
 Distribuzione geografica
Continente #
NA - Nord America 1.472
EU - Europa 933
AS - Asia 269
Continente sconosciuto - Info sul continente non disponibili 17
SA - Sud America 9
OC - Oceania 1
Totale 2.701
Nazione #
US - Stati Uniti d'America 1.347
GB - Regno Unito 257
IT - Italia 250
SE - Svezia 177
CN - Cina 144
CA - Canada 124
DE - Germania 74
RU - Federazione Russa 38
FR - Francia 36
BE - Belgio 34
VN - Vietnam 34
FI - Finlandia 33
HK - Hong Kong 32
IN - India 25
EU - Europa 17
SG - Singapore 17
JP - Giappone 11
UA - Ucraina 11
BR - Brasile 7
ES - Italia 7
NL - Olanda 4
CH - Svizzera 3
CZ - Repubblica Ceca 3
IE - Irlanda 3
AT - Austria 2
IR - Iran 2
KR - Corea 2
PE - Perù 2
KG - Kirghizistan 1
NZ - Nuova Zelanda 1
PA - Panama 1
RO - Romania 1
UZ - Uzbekistan 1
Totale 2.701
Città #
Chandler 513
Southend 130
San Mateo 126
Toronto 121
Boardman 112
New York 80
Ashburn 63
Berlin 47
Trenton 44
Rome 37
Brussels 34
Dong Ket 34
Beijing 33
Hong Kong 32
Helsinki 25
Ann Arbor 19
Las Vegas 19
Miami 17
Mountain View 17
Washington 16
Milan 15
Redwood City 15
Santa Clara 14
Marseille 13
Singapore 11
Bologna 10
Los Angeles 10
Lappeenranta 8
Málaga 7
Guangzhou 6
Mazzano Romano 5
Paris 5
Rockville 5
Shenzhen 5
Canale Monterano 4
Castel Gandolfo 4
Como 4
Dallas 4
Falls Church 4
Herzberg 4
Kyiv 4
Mumbai 4
Napoli 4
Saint-Fons 4
Tampa 4
Ciampino 3
Dublin 3
Gif-sur-yvette 3
Hanover 3
Zhengzhou 3
Angri 2
Borås 2
Cagliari 2
Castellana Grotte 2
Châteauneuf-le-rouge 2
Des Moines 2
Florence 2
Forlimpopoli 2
Fukuoka 2
Hamilton 2
Lima 2
Nuremberg 2
Padova 2
Piglio 2
Quargnento 2
Shanghai 2
Turin 2
Anzio 1
Auckland 1
Aversa 1
Bangalore 1
Bishkek 1
Botticino 1
Bracciano 1
Brindisi 1
Brno 1
Buffalo 1
Cambridge 1
Cava de' Tirreni 1
Chengdu 1
Chennai 1
Chicago 1
Cisterna di Latina 1
Council Bluffs 1
Desio 1
Forest City 1
Foshan 1
Genoa 1
Grosseto 1
Hangyang 1
Horia 1
Houston 1
Huizen 1
Hyderabad 1
Iglesias 1
Karlsruhe 1
Kish 1
Krems 1
Lanciano 1
Lerici 1
Totale 1.774
Nome #
Gestione del rischio in un impianto a fusione: l’approccio integrato della radioprotezione e della sicurezza per il progetto Sorgentina-RF 100
Analysis of the ZED-2 reactor for the benchmarking of newly measured Gadolinium capture cross-sections 96
Updated design and integration of the ancillary circuits for the European Test Blanket Systems 86
Preliminary assessment of radiolysis for the cooling water system in the rotating target of SORGENTINA-RF 81
BUGENDF70.BOLIB – An ENDF/B-VII.0 Broad-Group Coupled (47n+20 γ) Cross Section Library in FIDO-ANISN Format for LWR Shielding and Pressure Vessel Dosimetry Applications 80
BUGENDF70.BOLIB - An ENEA-Bologna ENDF/B-VII.0 Cross Section Library (47 n + 20 γ) in FIDO-ANISN Format for LWR Shielding and Pressure Vessel Dosimetry Applications 75
Start-up and shutdown thermomechanical transient analyses of the IFMIF European lithium target system 73
BUGJEFF311.BOLIB - A JEFF-3.1.1 Broad-Group Coupled (47 n + 20 γ) Cross Section Library in FIDO-ANISN Format for LWR Shielding and Pressure Vessel Dosimetry Applications 71
Preliminary evaluations of the environmental impact for the production of 99Mo by fusion neutrons 70
Nuclear assessment of the IFMIF-DONES lithium target system 67
The design of the DONES lithium target system 66
Rapporto preliminare del progetto del target di IFMIF comprensivo di disegni, analisi numeriche e valutazione dei costi 65
Three-Dimensional (X,Y,Z) Deterministic Analysis of the PCA-Replica Neutron Shielding Benchmark Experiment Using the TORT-3.2 Code and Group Cross Section Libraries for LWR Shielding and Pressure Vessel Dosimetry 65
Nuclear analysis of the IFMIF European lithium target assembly system 62
PCA-Replica (H2O/Fe) Neutron Shielding Benchmark Experiment - Deterministic Analysis in Cartesian (X,Y,Z) Geometry Using the TORT-3.2 3D Transport Code and the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-96 Cross Section Libraries 62
BUGJEFF311.BOLIB (JEFF-3.1.1) and BUGENDF70.BOLIB (ENDF/B-VII.0) - Generation Methodology and Preliminary Testing of two ENEA-Bologna Group Cross Section Libraries for LWR Shielding and Pressure Vessel Dosimetry 61
Experimental fusion material photon and electron decay heat measurements: Its use for activation codes validation 60
ANITA-IEAF activation code package - Updating of the decay and cross section data libraries and validation on the experimental data from the Karlsruhe Isochronous Cyclotron 60
The European contribution to the development and validation activities for the design of IFMIF lithium facility 60
ANITA-IEAF: an intermediate energy neutron activation system 59
BUGJEFF311.BOLIB (JEFF-3.1.1) and BUGENDF70.BOLIB (ENDF/B-VII.0) - Generation Methodology and Preliminary Testing of Two ENEA-Bologna Group Cross Section Libraries for LWR Shielding and Pressure Vessel Dosimetry 59
The accomplishment of the Engineering Design Activities of IFMIF/EVEDA: The European-Japanese project towards a Li(d,xn) fusion relevant neutron source 57
The SCALENEA-1 multipurpose Sn calculation sequence for application in fusion field: Main features and its validation based on experimental data from a low-level waste repository 57
Neutronics of the IFMIF-DONES irradiation facility 57
VITENDF70.BOLIB - An ENDF/B- VII.O Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format 56
Production of the ANITA-NC system able to treat material activation due to neutral or charged particles 56
Hydro-thermo analysis of Li flow over IFMIF geometry 55
ANITA-IEAF: A code package for performing fusion material transmutation and activation analysis induced by intermediate energy neutrons 54
Analysis of the thermomechanical behavior of the IFMIF bayonet target assembly under design loading scenarios 54
VITJEFF32.BOLIB - An ENEA-Bologna Fine-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format Based on JEFF-3.2 Data 53
ANITA-IEAF intermediate energy neutron activation package: updating and validation of the decay and cross section data libraries 50
Updating of the Libraries Included in the ANITA-2000 Code Package on the Basis of the JEFF-3.1.1 Radioactive Decay Data Library 50
VITJEFF32.BOLIB - A JEFF-3.2 Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format for Nuclear Fission Applications 49
On the Figure of Merit in Neutron Time-of-Flight Measurements 46
ANITA-2000 activation code package - Updating of the decay data libraries and validation on the experimental data of the 14 MeV Frascati Neutron Generator 46
Processing and Validation of JEFF-3.1.1 and ENDF/B-VII.0 Group-Wise Cross Section Libraries for Shielding Calculations 46
Preliminary evaluations of the environmental impact for the production of 99Mo by fusion neutrons 45
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-B7 Broad-Group Libraries on the PCA-Replica (H2O/Fe) Neutron Shielding Benchmark Experiment 45
Processing and validation of JEFF-3.1.1 and ENDF/B-VII.0 group-wise cross section libraries for shielding calculations 45
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-96 Cross Section Libraries on the PCA-Replica (Water/Iron) Neutron Shielding Benchmark Experiment 43
Engineering design and steady state thermomechanical analysis of the IFMIF European lithium target system 43
Production and testing of the ENEA-Bologna VITJEFF32.BOLIB (JEFF-3.2) multi-group (199 n + 42 γ) cross section library in AMPX format for nuclear fission applications 43
VITENDF70.BOLIB - An ENEA-Bologna Fine-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format Based on ENDF/B - VII.0 Data 40
Valutazioni preliminari dell’impatto ambientale degli effluenti liquidi dovuti alla produzione di 99Mo mediante neutroni da fusione 40
Three-Dimensional (X,Y,Z) Deterministic Analysis of the PCA-Replica Neutron Shielding Benchmark Experiment using the TORT-3.2 Code and Group Cross Section Libraries for LWR Shielding and Pressure Vessel Dosimetry 39
Validation of the updated decay data libraries of the ANITA-2000 activation code package on experimental data produced by FNS-JAERI 38
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-B7 broad-group libraries on the PCA-Replica (H2O/Fe) neutron shielding benchmark experiment 34
The 64Zn-based production route to 64Cu β ±emitter using accelerator-driven 14 MeV fusion neutrons 12
Totale 2.731
Categoria #
all - tutte 18.862
article - articoli 0
book - libri 0
conference - conferenze 0
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 18.862


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/202046 0 0 0 0 0 7 11 4 1 17 1 5
2020/2021362 0 12 1 3 89 4 8 42 23 11 126 43
2021/2022578 15 127 21 24 63 8 32 158 43 4 37 46
2022/2023979 60 226 67 140 49 161 3 63 127 34 32 17
2023/2024596 36 24 60 17 78 117 19 50 80 27 18 70
2024/2025170 22 148 0 0 0 0 0 0 0 0 0 0
Totale 2.731