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 #
NA - Nord America 2.746
EU - Europa 2.631
AS - Asia 990
SA - Sud America 321
AF - Africa 15
OC - Oceania 7
Continente sconosciuto - Info sul continente non disponibili 6
Totale 6.716
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Nazione #
US - Stati Uniti d'America 2.570
IT - Italia 838
CN - Cina 366
GB - Regno Unito 343
SG - Singapore 341
DE - Germania 331
BR - Brasile 280
SE - Svezia 268
RU - Federazione Russa 228
AT - Austria 165
CA - Canada 165
HK - Hong Kong 154
FI - Finlandia 124
FR - Francia 123
BE - Belgio 55
NL - Olanda 38
PT - Portogallo 24
IN - India 21
JP - Giappone 20
UA - Ucraina 13
ES - Italia 12
BD - Bangladesh 10
IQ - Iraq 10
SI - Slovenia 10
EC - Ecuador 9
LT - Lituania 9
AR - Argentina 7
CH - Svizzera 7
CL - Cile 7
PL - Polonia 7
TR - Turchia 7
CZ - Repubblica Ceca 6
EU - Europa 6
GR - Grecia 6
MX - Messico 6
PK - Pakistan 6
UZ - Uzbekistan 6
IE - Irlanda 5
NZ - Nuova Zelanda 5
RO - Romania 5
ZA - Sudafrica 5
AL - Albania 4
CO - Colombia 4
JO - Giordania 4
OM - Oman 4
PE - Perù 4
PY - Paraguay 4
SA - Arabia Saudita 4
AZ - Azerbaigian 3
BO - Bolivia 3
DZ - Algeria 3
IR - Iran 3
KG - Kirghizistan 3
KR - Corea 3
LK - Sri Lanka 3
MA - Marocco 3
PH - Filippine 3
AE - Emirati Arabi Uniti 2
AM - Armenia 2
AU - Australia 2
CI - Costa d'Avorio 2
DK - Danimarca 2
IL - Israele 2
KE - Kenya 2
NO - Norvegia 2
PA - Panama 2
PS - Palestinian Territory 2
VE - Venezuela 2
VN - Vietnam 2
BA - Bosnia-Erzegovina 1
BH - Bahrain 1
CR - Costa Rica 1
DO - Repubblica Dominicana 1
EE - Estonia 1
GE - Georgia 1
GT - Guatemala 1
HR - Croazia 1
HU - Ungheria 1
ID - Indonesia 1
IS - Islanda 1
KZ - Kazakistan 1
LA - Repubblica Popolare Democratica del Laos 1
MD - Moldavia 1
MY - Malesia 1
NP - Nepal 1
SY - Repubblica araba siriana 1
TW - Taiwan 1
UY - Uruguay 1
Totale 6.716
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Città #
Chandler 772
Rome 241
Santa Clara 225
Boardman 180
San Mateo 171
Southend 163
Toronto 159
Ashburn 154
Hong Kong 148
The Dalles 142
New York 137
Singapore 124
Hamburg 117
Vienna 107
Beijing 86
Berlin 67
Helsinki 67
Brussels 52
Lappeenranta 52
Trenton 51
Milan 49
Los Angeles 35
Miami 33
Wilmington 33
Las Vegas 31
Marseille 31
Nuremberg 31
Frosinone 29
Aix-en-Provence 24
Falkenstein 22
Washington 21
Salerno 20
Amsterdam 19
São Paulo 19
Ann Arbor 18
Redwood City 18
Padova 17
Mountain View 16
Turin 14
Council Bluffs 13
Munich 13
Naples 12
Belo Horizonte 11
Chicago 11
Moscow 11
Düsseldorf 10
Genoa 10
Lisbon 10
London 10
Rio de Janeiro 10
Frankfurt am Main 8
Tokyo 8
Bologna 7
Ciampino 7
Shanghai 7
Brasília 6
Castel Gandolfo 6
Didcot 6
Garching 6
Istanbul 6
Ljubljana 6
Madrid 6
Paris 6
Dhaka 5
Hangzhou 5
Hanover 5
Mazzano Romano 5
Quito 5
Redmond 5
Rimini 5
San Diego 5
Tashkent 5
Amman 4
Auckland 4
Baghdad 4
Campinas 4
Cascais 4
Colombo 4
Falls Church 4
Guangzhou 4
Huizen 4
Karlsruhe 4
Lima 4
Monza 4
Nova Iguaçu 4
Perugia 4
Pomezia 4
Prague 4
Ribeirão Preto 4
Salvador 4
Santiago 4
Aachen 3
Agropoli 3
Bacoli 3
Baku 3
Bishkek 3
Bracciano 3
Brescia 3
Cerro Maggiore 3
Chengdu 3
Totale 4.049
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Nome #
DTT - Divertor Tokamak Test facility - Interim Design Report 555
Improved neutron activation dosimetry for fusion 181
A review of radioactive wastes production and potential environmental releases at experimental nuclear fusion facilities 154
Calibration and test of a 6LiF-diamond detector for the HCPB mock-up experiment at JET 146
Rifiuti radioattivi e rilasci degli impianti a fusione nucleare 138
Radiation Protection Design and Licensing for an Experimental Fusion Facility: The Italian and European Approaches 127
Application of ADVANTG to the JET3 – NEXP streaming benchmark experiment 123
Shutdown dose rate studies for the DTE2 campaign at JET 114
Nuclear design of Divertor Tokamak Test (DTT) facility 108
Neutronics study for DTT tokamak building 105
Measurement of delayed neutron emission from water activated by 14 MeV neutrons in a FW mock-up of ITER 105
DTT's Role, Characteristics Design Status 105
Role of Italian DTT in the power exhaust implementation strategy 104
DEMO port plug design and integration studies 103
Development of the advanced D1S for shutdown dose rate calculations in fusion reactors 102
Impact of the layout of the ITER Radial Neutron Camera in-port system on the measurement of the neutron emissivity profile 100
Ionizing radiation monitoring requirements at the Divertor Tokamak Test facility 98
Re-analysis of HCPB/HCLL blanket mock-up experiments using recent nuclear data libraries 97
The deuterium-tritium fuel cycle in tokamak devices 96
Computational evaluation of N-16 measurements for a 14 MeV neutron irradiation of an ITER first wall component with water circuit 96
Conceptual design studies for the European DEMO divertor: Rationale and first results 95
Pre-analysis of the WCLL breeding blanket mock-up neutronics experiment at the frascati neutron generator 93
Experience of handling beryllium, tritium and activated components from JET ITER like wall 92
Applications of McCad for the automatic generation of MCNP 3D models in fusion neutronics 91
Benchmarking of the 3-D CAD-based Discrete Ordinates code "aTTILA" for dose rate calculations against experiments and Monte Carlo calculations 90
Neutronics studies for the novel design of lower port in DEMO 90
Eurofusion-DEMO Divertor - Cassette Design and Integration 90
The radiological source terms in a nuclear fusion experimental facility 89
Divertor Tokamak Test facility project: status of design and implementation 87
Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project 86
The joint evaluated fission and fusion nuclear data library, JEFF-3.3 85
Neutronics requirements for a DEMO fusion power plant 81
Feasibility study of validating activation corrosion products calculations in cooling water loops at JET 81
Neutronics related integration studies of EU-DEMO pellet injection system 81
Review and validation of shutdown dose rate estimation techniques for application to iter 80
Nuclear analysis of the Single Module Segment WCLL DEMO 80
Neutron streaming analyses and shielding optimization through ECRH openings in DTT Tokamak building 80
Nuclear analysis of the ITER full-tungsten divertor 79
Characterization of a GEM-based fast neutron detector 78
Nuclear analysis of the Water cooled lithium lead DEMO reactor 78
Neutronic analyses in support of the conceptual design of the DTT tokamak radial neutron camera 77
Nuclear loads and nuclear shielding performance of EU DEMO divertor: A comparative neutronics evaluation of two interim design options 77
Neutronics experiments, radiation detectors and nuclear techniques development in the EU in support of the TBM design for ITER 75
The mcCad code for the automatic generation of MCNP 3-D models: Applications in fusion neutronics 74
TLD calibration for neutron fluence measurements at JET fusion facility 74
Developments and needs in nuclear analysis of fusion technology 74
Nuclear analyses for the design of the ITER-like plasma facing components vertical targets of the DEMO divertor 74
Measurement of the 16,17O(n,p)16,17N cross sections for validating the water activation experiment for ITER at the Frascati neutron generator 73
Parametric study of the influence of First Wall cooling water on the Water Cooled Lithium Lead Breeding Blanket nuclear response 73
Nuclear analysis of the ITER Cryopump Ports 71
Pre-analysis of the copper neutronics benchmark experiment for nuclear data validation 71
Neutronics assessment of EU DEMO alternative divertor configurations 70
Results of an integration study of a diagnostics port plug in ITER 70
Development of a Novel MCNP-OSCAR Fusion Interface for the 3-D Assessment of Gamma Dose Due to the Activated Corrosion Products 69
Nuclear performances of the water-cooled lithium lead DEMO reactor: Neutronic analysis on a fully heterogeneous model 68
Progress in development of advanced D1S dynamic code for three-dimensional shutdown dose rate calculations 68
Status of ITER TBM port plug conceptual design and analyses 67
Divertor options impact on DEMO nuclear performances 64
Overview of experimental benchmarking of shutdown dose rate calculations in fusion devices, invited 64
Comparison of neutron flux streaming calculations to the 2019-2020 JET Experimental Deuterium-Deuterium Results 64
Evaluation of the neutron activation of JET in-vessel components following DT irradiation 63
Disruption prediction with artificial intelligence techniques in tokamak plasmas 60
ITER tungsten divertor design development and qualification program 60
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 59
Neutronic analyses for the equatorial diagnostic port plug #12 in ITER 59
Shutdown dose rate assessment with the Advanced D1S method: Development, applications and validation 54
Nuclear Analyses for the Assessment of the Loads on the ITER Radial Neutron Camera In-Port System and Evaluation of Its Measurement Performances 53
Novel approach for efficient mesh based Monte Carlo shutdown dose rate calculations 52
Preparation of a water activation experiment at JET to support ITER 50
Nuclear analysis of ITER Test Blanket Module Port Plug 50
Divertor of the European DEMO: Engineering and technologies for power exhaust 48
Neutronic challenges for the estimation of shut-down dose rates in ITER ports, invited 47
Neutronic and Shielding Analyses for the DTT Electronics 46
Dose Rate Measurements During the Tritium Campaign at JET and Diagnostic Improvements for the Deuterium–Tritium Experiments 44
Nuclear Analyses of ITER Diagnostics Lower Ports 39
Analysis of discrepancies between D1S and R2S results of 2016 DD JET Campaign 38
Overview of neutron measurements in JET fusion device 37
A control oriented strategy of disruption prediction to avoid the configuration collapse of tokamak reactors 36
Nuclear Analysis for the Upper Ports in the NB Cell in ITER 36
EUROfusion contributions to ITER nuclear operation 29
Measurement of tritium production in the helium cooled pebble bed test blanket module mock-up at JET during DTE2 18
ITER materials irradiation within the D-T neutron environment at JET: post-irradiation radioactivity analysis following the DTE2 experimental campaign 6
Totale 6.864
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Categoria #
all - tutte 41.200
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 41.200
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/20207 0 0 0 0 0 0 0 0 0 0 2 5
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
2024/20252.450 28 234 92 91 342 151 225 333 413 318 223 0
Totale 6.864