ENEA-IRIS Open Archive è l’archivio della produzione scientifica dell'ENEA, realizzato con l'obiettivo di raccogliere, catalogare e rendere facilmente accessibili in rete i risultati della ricerca. Gli autori dell’ENEA provvedono a depositare le proprie pubblicazioni (articoli su rivista, presentazioni a congressi, report, ecc.). In particolare, quelle finanziate dalla Commissione Europea nell’ambito del programma H2020 (che prevede il deposito obbligatorio in un Repository), una volta caricate, vengono automaticamente importate dal portale europeo OpenAIRE. È possibile inserire, o importare direttamente dalle banche dati previste, le informazioni descrittive del documento e anche allegare, ove consentito dalla normativa sul diritto d'autore, il testo completo della pubblicazione.

ENEA-IRIS Open Archive utilizza la piattaforma IRIS (Institutional Research Information System) sviluppata da CINECA.

FRISONI, MANUELA
 Distribuzione geografica
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Continente #
NA - Nord America 1.656
EU - Europa 1.074
AS - Asia 462
SA - Sud America 31
Continente sconosciuto - Info sul continente non disponibili 17
AF - Africa 2
OC - Oceania 1
Totale 3.243
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Nazione #
US - Stati Uniti d'America 1.526
IT - Italia 281
GB - Regno Unito 268
CN - Cina 199
SE - Svezia 180
CA - Canada 128
DE - Germania 122
SG - Singapore 104
HK - Hong Kong 72
FI - Finlandia 61
RU - Federazione Russa 44
FR - Francia 36
BE - Belgio 35
VN - Vietnam 35
BR - Brasile 28
IN - India 25
EU - Europa 17
NL - Olanda 14
UA - Ucraina 12
JP - Giappone 11
ES - Italia 7
IR - Iran 5
AT - Austria 3
CH - Svizzera 3
CZ - Repubblica Ceca 3
IE - Irlanda 3
KR - Corea 2
PE - Perù 2
TR - Turchia 2
AZ - Azerbaigian 1
BD - Bangladesh 1
CR - Costa Rica 1
KG - Kirghizistan 1
KW - Kuwait 1
KZ - Kazakistan 1
LT - Lituania 1
MA - Marocco 1
NZ - Nuova Zelanda 1
PA - Panama 1
PS - Palestinian Territory 1
RO - Romania 1
UY - Uruguay 1
UZ - Uzbekistan 1
ZA - Sudafrica 1
Totale 3.243
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Città #
Chandler 523
Santa Clara 156
Southend 133
San Mateo 129
Toronto 125
Boardman 115
New York 83
Singapore 73
Hong Kong 72
Ashburn 66
Helsinki 53
Rome 50
Berlin 48
Trenton 45
Munich 44
Beijing 37
Brussels 35
Dong Ket 34
Ann Arbor 19
Las Vegas 19
Miami 18
Milan 18
Mountain View 17
Washington 17
Redwood City 15
Marseille 13
Los Angeles 12
Bologna 10
Amsterdam 9
Guangzhou 8
Lappeenranta 8
Málaga 7
Mazzano Romano 5
Napoli 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
Nuremberg 4
Saint-Fons 4
Shanghai 4
Tampa 4
Ciampino 3
Dublin 3
Gif-sur-yvette 3
Hanover 3
Moscow 3
Zhengzhou 3
Angri 2
Borås 2
Cagliari 2
Castellana Grotte 2
Chengdu 2
Châteauneuf-le-rouge 2
Des Moines 2
Florence 2
Forlimpopoli 2
Foshan 2
Frankfurt am Main 2
Fukuoka 2
Hamilton 2
Kunming 2
Lima 2
London 2
Padova 2
Piglio 2
Quargnento 2
Rio de Janeiro 2
Turin 2
Anzio 1
Atibaia 1
Auckland 1
Aversa 1
Baku 1
Bangalore 1
Belford Roxo 1
Belo Horizonte 1
Betim 1
Bishkek 1
Boa Viagem 1
Botticino 1
Bracciano 1
Brindisi 1
Brno 1
Buffalo 1
Bursa 1
Cambridge 1
Cava de' Tirreni 1
Chennai 1
Cherkasy 1
Chicago 1
Cisterna di Latina 1
Coroatá 1
Totale 2.168
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Nome #
Preliminary assessment of radiolysis for the cooling water system in the rotating target of SORGENTINA-RF 159
Analysis of the ZED-2 reactor for the benchmarking of newly measured Gadolinium capture cross-sections 119
Gestione del rischio in un impianto a fusione: l’approccio integrato della radioprotezione e della sicurezza per il progetto Sorgentina-RF 108
Updated design and integration of the ancillary circuits for the European Test Blanket Systems 95
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 88
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 85
Preliminary evaluations of the environmental impact for the production of 99Mo by fusion neutrons 80
Start-up and shutdown thermomechanical transient analyses of the IFMIF European lithium target system 79
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 78
Processing and Validation of JEFF-3.1.1 and ENDF/B-VII.0 Group-Wise Cross Section Libraries for Shielding Calculations 77
Rapporto preliminare del progetto del target di IFMIF comprensivo di disegni, analisi numeriche e valutazione dei costi 74
Nuclear assessment of the IFMIF-DONES lithium target system 74
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 72
The design of the DONES lithium target system 72
The accomplishment of the Engineering Design Activities of IFMIF/EVEDA: The European-Japanese project towards a Li(d,xn) fusion relevant neutron source 71
Nuclear analysis of the IFMIF European lithium target assembly system 69
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 69
The European contribution to the development and validation activities for the design of IFMIF lithium facility 69
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 69
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 69
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 69
Experimental fusion material photon and electron decay heat measurements: Its use for activation codes validation 68
ANITA-IEAF: an intermediate energy neutron activation system 68
Analysis of the thermomechanical behavior of the IFMIF bayonet target assembly under design loading scenarios 65
Hydro-thermo analysis of Li flow over IFMIF geometry 63
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 62
VITENDF70.BOLIB - An ENDF/B- VII.O Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format 62
Neutronics of the IFMIF-DONES irradiation facility 62
ANITA-2000 activation code package - Updating of the decay data libraries and validation on the experimental data of the 14 MeV Frascati Neutron Generator 61
VITJEFF32.BOLIB - An ENEA-Bologna Fine-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format Based on JEFF-3.2 Data 61
Updating of the Libraries Included in the ANITA-2000 Code Package on the Basis of the JEFF-3.1.1 Radioactive Decay Data Library 61
ANITA-IEAF: A code package for performing fusion material transmutation and activation analysis induced by intermediate energy neutrons 60
Production of the ANITA-NC system able to treat material activation due to neutral or charged particles 59
ANITA-IEAF intermediate energy neutron activation package: updating and validation of the decay and cross section data libraries 57
VITJEFF32.BOLIB - A JEFF-3.2 Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format for Nuclear Fission Applications 56
Materials activation induced by high-energy neutrons: A comparison of ANITA-IEAF calculation with measurements from the Karlsruhe Isochronous Cyclotron 55
On the Figure of Merit in Neutron Time-of-Flight Measurements 53
Engineering design and steady state thermomechanical analysis of the IFMIF European lithium target system 53
Preliminary evaluations of the environmental impact for the production of 99Mo by fusion neutrons 51
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-96 Cross Section Libraries on the PCA-Replica (Water/Iron) Neutron Shielding Benchmark Experiment 50
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-B7 Broad-Group Libraries on the PCA-Replica (H2O/Fe) Neutron Shielding Benchmark Experiment 49
Processing and validation of JEFF-3.1.1 and ENDF/B-VII.0 group-wise cross section libraries for shielding calculations 49
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 48
Valutazioni preliminari dell’impatto ambientale degli effluenti liquidi dovuti alla produzione di 99Mo mediante neutroni da fusione 48
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 45
Validation of the updated decay data libraries of the ANITA-2000 activation code package on experimental data produced by FNS-JAERI 44
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 44
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-B7 broad-group libraries on the PCA-Replica (H2O/Fe) neutron shielding benchmark experiment 44
The 64Zn-based production route to 64Cu β ±emitter using accelerator-driven 14 MeV fusion neutrons 32
Totale 3.275
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Categoria #
all - tutte 22.167
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 22.167
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/202039 0 0 0 0 0 0 11 4 1 17 1 5
2020/2021368 0 12 1 3 91 4 8 43 23 11 129 43
2021/2022588 15 130 21 24 64 8 32 162 43 4 38 47
2022/2023994 60 230 67 143 50 165 3 63 128 35 33 17
2023/2024606 36 25 61 17 79 120 19 50 81 28 18 72
2024/2025673 22 154 69 41 208 76 103 0 0 0 0 0
Totale 3.275