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.

VILLARI, ROSARIA
 Distribuzione geografica
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Continente #
EU - Europa 7.357
NA - Nord America 3.028
AS - Asia 1.525
SA - Sud America 395
AF - Africa 26
OC - Oceania 7
Continente sconosciuto - Info sul continente non disponibili 6
Totale 12.344
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Nazione #
RU - Federazione Russa 4.704
US - Stati Uniti d'America 2.835
IT - Italia 856
SG - Singapore 684
DE - Germania 434
CN - Cina 428
GB - Regno Unito 359
BR - Brasile 349
SE - Svezia 271
CA - Canada 175
AT - Austria 167
FI - Finlandia 159
FR - Francia 159
HK - Hong Kong 156
JP - Giappone 104
BE - Belgio 55
NL - Olanda 42
IN - India 30
PT - Portogallo 24
PL - Polonia 22
ES - Italia 18
UA - Ucraina 18
BD - Bangladesh 17
IQ - Iraq 17
EC - Ecuador 12
TR - Turchia 12
LT - Lituania 11
MX - Messico 11
SI - Slovenia 10
UZ - Uzbekistan 10
ZA - Sudafrica 9
AR - Argentina 8
CH - Svizzera 8
CZ - Repubblica Ceca 8
CL - Cile 7
PK - Pakistan 7
EU - Europa 6
GR - Grecia 6
MA - Marocco 6
SA - Arabia Saudita 6
VN - Vietnam 6
AL - Albania 5
IE - Irlanda 5
JO - Giordania 5
NZ - Nuova Zelanda 5
PY - Paraguay 5
RO - Romania 5
AZ - Azerbaigian 4
CO - Colombia 4
OM - Oman 4
PE - Perù 4
AM - Armenia 3
BO - Bolivia 3
DZ - Algeria 3
IR - Iran 3
KE - Kenya 3
KG - Kirghizistan 3
KR - Corea 3
LK - Sri Lanka 3
PH - Filippine 3
PS - Palestinian Territory 3
AE - Emirati Arabi Uniti 2
AU - Australia 2
CI - Costa d'Avorio 2
DK - Danimarca 2
IL - Israele 2
KZ - Kazakistan 2
NO - Norvegia 2
PA - Panama 2
VE - Venezuela 2
BA - Bosnia-Erzegovina 1
BH - Bahrain 1
BY - Bielorussia 1
CR - Costa Rica 1
DO - Repubblica Dominicana 1
EE - Estonia 1
EG - Egitto 1
ET - Etiopia 1
GE - Georgia 1
GT - Guatemala 1
HN - Honduras 1
HR - Croazia 1
HU - Ungheria 1
ID - Indonesia 1
IS - Islanda 1
LA - Repubblica Popolare Democratica del Laos 1
MD - Moldavia 1
MY - Malesia 1
NP - Nepal 1
SY - Repubblica araba siriana 1
TN - Tunisia 1
TT - Trinidad e Tobago 1
TW - Taiwan 1
UY - Uruguay 1
Totale 12.344
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Città #
Moscow 1.057
Chandler 772
Singapore 291
Rome 245
Santa Clara 239
Boardman 180
Ashburn 173
San Mateo 171
Southend 163
Toronto 161
Hong Kong 150
New York 150
Beijing 145
The Dalles 143
Hamburg 117
Vienna 108
Munich 83
Helsinki 68
Berlin 67
Columbus 62
Brussels 52
Lappeenranta 52
Trenton 51
Milan 50
Los Angeles 42
Turku 37
Miami 33
Wilmington 33
Nuremberg 32
Las Vegas 31
Marseille 31
Frosinone 29
São Paulo 27
Aix-en-Provence 25
Falkenstein 23
Amsterdam 21
Washington 21
Salerno 20
Frankfurt am Main 19
Ann Arbor 18
Jülich 18
Redwood City 18
Padova 17
Mountain View 16
Turin 16
Chicago 15
Warsaw 15
Council Bluffs 14
Paris 14
Rio de Janeiro 14
London 12
Naples 12
Belo Horizonte 11
Tokyo 11
Boston 10
Brooklyn 10
Düsseldorf 10
Genoa 10
Lisbon 10
Dallas 8
San Francisco 8
Baghdad 7
Bologna 7
Ciampino 7
Shanghai 7
Tashkent 7
Brasília 6
Castel Gandolfo 6
Chennai 6
Dhaka 6
Didcot 6
Garching 6
Istanbul 6
Ljubljana 6
Madrid 6
Roubaix 6
Stockholm 6
Amman 5
Bexley 5
Campinas 5
Hangzhou 5
Hanover 5
Johannesburg 5
Louisville 5
Mazzano Romano 5
Montreal 5
Quito 5
Redmond 5
Rimini 5
San Diego 5
Atlanta 4
Auckland 4
Baku 4
Cascais 4
Colombo 4
Erbil 4
Falls Church 4
Fortaleza 4
Guangzhou 4
Guarulhos 4
Totale 5.667
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Nome #
DTT - Divertor Tokamak Test facility - Interim Design Report 624
Improved neutron activation dosimetry for fusion 249
Calibration and test of a 6LiF-diamond detector for the HCPB mock-up experiment at JET 224
A review of radioactive wastes production and potential environmental releases at experimental nuclear fusion facilities 224
Rifiuti radioattivi e rilasci degli impianti a fusione nucleare 207
Application of ADVANTG to the JET3 – NEXP streaming benchmark experiment 195
Radiation Protection Design and Licensing for an Experimental Fusion Facility: The Italian and European Approaches 190
Nuclear design of Divertor Tokamak Test (DTT) facility 186
Role of Italian DTT in the power exhaust implementation strategy 181
Shutdown dose rate studies for the DTE2 campaign at JET 180
DEMO port plug design and integration studies 172
Development of the advanced D1S for shutdown dose rate calculations in fusion reactors 171
Measurement of delayed neutron emission from water activated by 14 MeV neutrons in a FW mock-up of ITER 171
DTT's Role, Characteristics Design Status 171
Re-analysis of HCPB/HCLL blanket mock-up experiments using recent nuclear data libraries 170
Ionizing radiation monitoring requirements at the Divertor Tokamak Test facility 168
Divertor Tokamak Test facility project: status of design and implementation 166
Conceptual design studies for the European DEMO divertor: Rationale and first results 166
Computational evaluation of N-16 measurements for a 14 MeV neutron irradiation of an ITER first wall component with water circuit 166
Neutronics study for DTT tokamak building 162
Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project 162
Benchmarking of the 3-D CAD-based Discrete Ordinates code "aTTILA" for dose rate calculations against experiments and Monte Carlo calculations 160
Measurement of the 16,17O(n,p)16,17N cross sections for validating the water activation experiment for ITER at the Frascati neutron generator 159
Pre-analysis of the WCLL breeding blanket mock-up neutronics experiment at the frascati neutron generator 159
Feasibility study of validating activation corrosion products calculations in cooling water loops at JET 155
Eurofusion-DEMO Divertor - Cassette Design and Integration 155
Impact of the layout of the ITER Radial Neutron Camera in-port system on the measurement of the neutron emissivity profile 154
Experience of handling beryllium, tritium and activated components from JET ITER like wall 154
The deuterium-tritium fuel cycle in tokamak devices 154
Applications of McCad for the automatic generation of MCNP 3D models in fusion neutronics 152
The radiological source terms in a nuclear fusion experimental facility 151
The joint evaluated fission and fusion nuclear data library, JEFF-3.3 149
Development of a Novel MCNP-OSCAR Fusion Interface for the 3-D Assessment of Gamma Dose Due to the Activated Corrosion Products 148
Neutronics studies for the novel design of lower port in DEMO 148
Neutronics related integration studies of EU-DEMO pellet injection system 147
Neutron streaming analyses and shielding optimization through ECRH openings in DTT Tokamak building 147
Developments and needs in nuclear analysis of fusion technology 146
Nuclear analysis of the Single Module Segment WCLL DEMO 145
Disruption prediction with artificial intelligence techniques in tokamak plasmas 144
Characterization of a GEM-based fast neutron detector 144
Review and validation of shutdown dose rate estimation techniques for application to iter 143
Nuclear loads and nuclear shielding performance of EU DEMO divertor: A comparative neutronics evaluation of two interim design options 143
Nuclear analyses for the design of the ITER-like plasma facing components vertical targets of the DEMO divertor 143
TLD calibration for neutron fluence measurements at JET fusion facility 142
Nuclear analysis of the Water cooled lithium lead DEMO reactor 141
Neutronics requirements for a DEMO fusion power plant 140
Divertor options impact on DEMO nuclear performances 140
Nuclear performances of the water-cooled lithium lead DEMO reactor: Neutronic analysis on a fully heterogeneous model 138
Neutronic analyses for the equatorial diagnostic port plug #12 in ITER 137
Neutronics experiments, radiation detectors and nuclear techniques development in the EU in support of the TBM design for ITER 136
Nuclear analysis of the ITER full-tungsten divertor 136
Neutronic analyses in support of the conceptual design of the DTT tokamak radial neutron camera 136
Neutronics analysis and activation calculation for tungsten used in the DEMO divertor targets: A comparative study between the effects of WCLL and HCPB blanket, different W compositions and chromium 134
Parametric study of the influence of First Wall cooling water on the Water Cooled Lithium Lead Breeding Blanket nuclear response 134
Comparison of neutron flux streaming calculations to the 2019-2020 JET Experimental Deuterium-Deuterium Results 134
Nuclear Analyses for the Assessment of the Loads on the ITER Radial Neutron Camera In-Port System and Evaluation of Its Measurement Performances 132
Pre-analysis of the copper neutronics benchmark experiment for nuclear data validation 132
Status of ITER TBM port plug conceptual design and analyses 131
Results of an integration study of a diagnostics port plug in ITER 131
Nuclear analysis of the ITER Cryopump Ports 130
The mcCad code for the automatic generation of MCNP 3-D models: Applications in fusion neutronics 130
Neutronics assessment of EU DEMO alternative divertor configurations 128
Overview of experimental benchmarking of shutdown dose rate calculations in fusion devices, invited 127
Progress in development of advanced D1S dynamic code for three-dimensional shutdown dose rate calculations 127
Divertor of the European DEMO: Engineering and technologies for power exhaust 126
Evaluation of the neutron activation of JET in-vessel components following DT irradiation 123
ITER tungsten divertor design development and qualification program 120
Neutronic and Shielding Analyses for the DTT Electronics 118
Shutdown dose rate assessment with the Advanced D1S method: Development, applications and validation 117
Novel approach for efficient mesh based Monte Carlo shutdown dose rate calculations 114
A control oriented strategy of disruption prediction to avoid the configuration collapse of tokamak reactors 112
Preparation of a water activation experiment at JET to support ITER 111
Nuclear analysis of ITER Test Blanket Module Port Plug 109
EUROfusion contributions to ITER nuclear operation 107
Dose Rate Measurements During the Tritium Campaign at JET and Diagnostic Improvements for the Deuterium–Tritium Experiments 100
Neutronic challenges for the estimation of shut-down dose rates in ITER ports, invited 100
Nuclear Analyses of ITER Diagnostics Lower Ports 99
Analysis of discrepancies between D1S and R2S results of 2016 DD JET Campaign 99
Overview of neutron measurements in JET fusion device 95
Nuclear Analysis for the Upper Ports in the NB Cell in ITER 94
Measurement of tritium production in the helium cooled pebble bed test blanket module mock-up at JET during DTE2 85
ITER materials irradiation within the D-T neutron environment at JET: post-irradiation radioactivity analysis following the DTE2 experimental campaign 77
Nuclear analyses for the integration of ITER equatorial Port 2 67
Insights from applications of the RSTM tool for coupled CFD-activation fluid simulation 50
Shutdown dose rate experiment at JET during DTE2 28
Characterisation of the neutron field for streaming analyses in TT operations at JET 26
Nuclear analyses in support of ITER ex-port Radial Neutron Camera design 5
Totale 12.503
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Categoria #
all - tutte 56.005
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 56.005
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021611 36 38 6 10 124 19 29 60 48 44 171 26
2021/2022879 19 191 14 53 94 28 31 166 92 32 54 105
2022/20231.725 135 344 104 251 97 284 30 128 201 38 55 58
2023/20241.084 58 21 105 42 139 201 26 110 103 75 62 142
2024/20257.315 28 234 92 91 342 151 225 333 413 318 2.163 2.925
2025/2026774 774 0 0 0 0 0 0 0 0 0 0 0
Totale 12.503