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.

PORFIRI, MARIA TERESA
 Distribuzione geografica
Salva come PNG Salva come JPEG
Continente #
NA - Nord America 1.182
EU - Europa 876
AS - Asia 412
SA - Sud America 152
AF - Africa 12
Continente sconosciuto - Info sul continente non disponibili 4
OC - Oceania 1
Totale 2.639
Salva come PNG Salva come JPEG
Nazione #
US - Stati Uniti d'America 1.092
CN - Cina 175
IT - Italia 169
GB - Regno Unito 167
SG - Singapore 141
BR - Brasile 134
SE - Svezia 131
RU - Federazione Russa 92
DE - Germania 89
CA - Canada 84
FI - Finlandia 69
FR - Francia 63
HK - Hong Kong 55
BE - Belgio 23
NL - Olanda 20
AT - Austria 10
ES - Italia 8
RO - Romania 8
GR - Grecia 7
CZ - Repubblica Ceca 6
IN - India 6
MA - Marocco 6
EC - Ecuador 5
JP - Giappone 5
BD - Bangladesh 4
EU - Europa 4
KZ - Kazakistan 4
MX - Messico 4
TR - Turchia 4
UA - Ucraina 4
AR - Argentina 3
IQ - Iraq 3
PL - Polonia 3
VE - Venezuela 3
VN - Vietnam 3
ZA - Sudafrica 3
CO - Colombia 2
KG - Kirghizistan 2
LT - Lituania 2
PK - Pakistan 2
AE - Emirati Arabi Uniti 1
AZ - Azerbaigian 1
BN - Brunei Darussalam 1
BO - Bolivia 1
CH - Svizzera 1
CL - Cile 1
DO - Repubblica Dominicana 1
DZ - Algeria 1
EG - Egitto 1
ID - Indonesia 1
IE - Irlanda 1
JM - Giamaica 1
JO - Giordania 1
LB - Libano 1
LU - Lussemburgo 1
NZ - Nuova Zelanda 1
OM - Oman 1
PE - Perù 1
PT - Portogallo 1
PY - Paraguay 1
RS - Serbia 1
TN - Tunisia 1
UY - Uruguay 1
UZ - Uzbekistan 1
Totale 2.639
Salva come PNG Salva come JPEG
Città #
Chandler 342
Santa Clara 99
Ashburn 87
Southend 84
Boardman 82
San Mateo 78
Toronto 68
Hong Kong 54
The Dalles 52
New York 49
Singapore 44
Lappeenranta 38
Beijing 35
Berlin 30
Helsinki 28
Rome 26
Aix-en-Provence 23
Brussels 23
Nuremberg 22
Miami 19
Milan 15
Trenton 14
Los Angeles 13
Amsterdam 10
Falls Church 9
Marseille 9
Falkenstein 8
Ottawa 8
Redwood City 8
Las Vegas 7
Raleigh 7
São Paulo 7
Washington 7
Madrid 6
Mountain View 6
Munich 6
Shanghai 6
Veniano 6
Ann Arbor 5
Dongguan 5
Wilmington 5
Catania 4
Council Bluffs 4
Kitchener 4
Pisa 4
Vienna 4
Belo Horizonte 3
Bracknell 3
Curitiba 3
Fiumicino 3
Guangzhou 3
Hradec Králové 3
Leopoldshafen 3
London 3
Maceió 3
Montegaldella 3
Moscow 3
Palermo 3
Ribeirão Preto 3
Rio de Janeiro 3
Salvador 3
Tokyo 3
Arlington 2
Astana 2
Atyrau 2
Bangalore 2
Brasília 2
Buffalo 2
Cagliari 2
Campinas 2
Casablanca 2
Catende 2
Contagem 2
Dhaka 2
Dong Ket 2
Dourados 2
Espoo 2
Granada 2
Guarulhos 2
Guayaquil 2
Ipatinga 2
Joinville 2
Kralupy nad Vltavou 2
Lincoln 2
Livorno 2
Manaus 2
Monfalcone 2
Naples 2
Nepean 2
Padova 2
Petrópolis 2
Piaseczno 2
Rabat 2
Redmond 2
Rockville 2
San Francesco al Campo 2
Santo André 2
Shenyang 2
Shenzhen 2
Stendal 2
Totale 1.594
Salva come PNG Salva come JPEG
Nome #
Tritium in tokamak devices: Safety issues 172
Preliminary safety analysis of an in-vessel LOCA for the EU-DEMO WCLL blanket concept 104
Large eddy simulation of Loss of Vacuum Accident in STARDUST facility 97
Conceptual design studies for the European DEMO divertor: Rationale and first results 95
Rapporto preliminare del progetto del target di IFMIF comprensivo di disegni, analisi numeriche e valutazione dei costi 93
Integration of safety in IFMIF-DONES design 92
Design basis accident analysis for the Ignitor experiment 91
Estimation of tritium and dust source term in european DEMOnstration fusion reactor during accident scenarios 91
Tritium in tokamak devices: Technological issues 90
Eurofusion-DEMO Divertor - Cassette Design and Integration 90
Preliminary sensitivity analysis for an ex-vessel LOCA without plasma shutdown for the EU DEMO WCLL blanket concept 87
The accomplishment of the Engineering Design Activities of IFMIF/EVEDA: The European-Japanese project towards a Li(d,xn) fusion relevant neutron source 86
The European contribution to the development and validation activities for the design of IFMIF lithium facility 83
ECART analysis of the STARDUST dust resuspension tests with an obstacle presence 83
Tritium and dust source term inventory evaluation issues in the European DEMO reactor concepts 82
ICE layer growth on a cryogenic surface in a fusion reactor during a loss of water event 79
Dust mobilization experiments in the context of the fusion plants - STARDUST facility 78
Exploratory fire analysis in DONES lithium system 77
Integrated design of breeding blanket and ancillary systems related to the use of helium or water as a coolant and impact on the overall plant design 76
Ex-vessel break in ITER divertor cooling loop analysis with the ECART code 75
Experimental and numerical analysis of the air inflow technique for dust removal from the vacuum vessel of a tokamak machine 71
Analysis of an ex-vessel break in the ITER divertor cooling loop 71
Modeling of a confinement bypass accident with CONSEN, a fast-running code for safety analyses in fusion reactors 71
Ingress of Coolant Event simulation with TRACE code with accuracy evaluation and coupled DAKOTA Uncertainty Analysis 71
Numerical study on Ingress of Coolant Event experiments with CONSEN code 68
DEMO Divertor preliminary safety assessment 63
Validation of the ECART code for the safety analysis of fusion reactors 63
Numerical simulation of an out-vessel loss of coolant from the breeder primary loop due to large rupture of tubes in a primary heat exchanger in the demo wcll concept 63
Supporting analysis for WCLL test blanket system safety 62
Disruption prediction with artificial intelligence techniques in tokamak plasmas 60
Safety assessment for EU DEMO – Achievements and open issues in view of a generic site safety report 60
DEMO Divertor Cassette and Plasma facing Unit in Vessel Loss-of-Coolant Accident 55
Divertor of the European DEMO: Engineering and technologies for power exhaust 48
DEMO – The main achievements of the Pre – Concept phase of the safety and environmental work package and the development of the GSSR 48
Totale 2.695
Salva come PNG Salva come JPEG
Categoria #
all - tutte 17.671
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 17.671
Salva come PNG Salva come JPEG


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/20202 0 0 0 0 0 0 0 0 0 0 0 2
2020/2021198 1 0 0 3 45 0 6 26 8 15 85 9
2021/2022370 8 84 3 36 39 9 20 82 27 6 26 30
2022/2023638 54 125 55 92 23 120 11 42 85 14 6 11
2023/2024508 22 16 50 25 47 97 15 62 44 40 27 63
2024/2025958 12 108 50 56 138 53 99 136 128 99 79 0
Totale 2.695