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
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Continente #
EU - Europa 2.830
NA - Nord America 2.285
AS - Asia 1.177
SA - Sud America 208
AF - Africa 39
Continente sconosciuto - Info sul continente non disponibili 4
OC - Oceania 3
Totale 6.546
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Nazione #
US - Stati Uniti d'America 2.171
RU - Federazione Russa 1.882
SG - Singapore 538
CN - Cina 385
GB - Regno Unito 198
IT - Italia 192
BR - Brasile 184
SE - Svezia 138
DE - Germania 117
CA - Canada 93
FR - Francia 90
FI - Finlandia 79
HK - Hong Kong 72
JP - Giappone 46
KR - Corea 36
MA - Marocco 27
NL - Olanda 27
IN - India 24
BE - Belgio 23
PL - Polonia 22
VN - Vietnam 22
MX - Messico 13
AT - Austria 11
BD - Bangladesh 11
ES - Italia 11
RO - Romania 8
CZ - Repubblica Ceca 7
GR - Grecia 7
TR - Turchia 7
ZA - Sudafrica 6
EC - Ecuador 5
IQ - Iraq 5
AR - Argentina 4
CL - Cile 4
EU - Europa 4
KZ - Kazakistan 4
LT - Lituania 4
UA - Ucraina 4
CO - Colombia 3
CR - Costa Rica 3
ID - Indonesia 3
IE - Irlanda 3
KG - Kirghizistan 3
PK - Pakistan 3
VE - Venezuela 3
AU - Australia 2
CH - Svizzera 2
MY - Malesia 2
PY - Paraguay 2
SA - Arabia Saudita 2
UZ - Uzbekistan 2
AE - Emirati Arabi Uniti 1
AM - Armenia 1
AZ - Azerbaigian 1
BB - Barbados 1
BN - Brunei Darussalam 1
BO - Bolivia 1
CI - Costa d'Avorio 1
CU - Cuba 1
DM - Dominica 1
DO - Repubblica Dominicana 1
DZ - Algeria 1
EG - Egitto 1
ET - Etiopia 1
HU - Ungheria 1
JM - Giamaica 1
JO - Giordania 1
LB - Libano 1
LU - Lussemburgo 1
NP - Nepal 1
NZ - Nuova Zelanda 1
OM - Oman 1
PE - Perù 1
PH - Filippine 1
PT - Portogallo 1
RS - Serbia 1
SD - Sudan 1
SK - Slovacchia (Repubblica Slovacca) 1
SY - Repubblica araba siriana 1
TH - Thailandia 1
TN - Tunisia 1
TW - Taiwan 1
UY - Uruguay 1
Totale 6.546
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Città #
Dallas 755
Moscow 415
Chandler 342
Singapore 249
Ashburn 150
Santa Clara 112
Hefei 103
Beijing 84
Southend 84
Boardman 82
San Mateo 78
Hong Kong 71
New York 71
Toronto 69
The Dalles 61
Lappeenranta 41
Seoul 35
Los Angeles 34
Berlin 30
Rome 30
Helsinki 28
Columbus 26
Munich 26
Aix-en-Provence 24
Brussels 23
Nuremberg 23
Casablanca 22
Miami 20
Milan 19
São Paulo 16
Warsaw 15
Trenton 14
Amsterdam 13
Council Bluffs 12
London 12
Boston 9
Chennai 9
Falls Church 9
Marseille 9
Tokyo 9
Brooklyn 8
Falkenstein 8
Frankfurt am Main 8
Las Vegas 8
Ottawa 8
Redwood City 8
Turku 8
Paris 7
Poplar 7
Raleigh 7
Stockholm 7
Washington 7
Atlanta 6
Houston 6
Madrid 6
Montreal 6
Mountain View 6
Pisa 6
Rio de Janeiro 6
Shanghai 6
Veniano 6
Ann Arbor 5
Chicago 5
Denver 5
Dongguan 5
Ho Chi Minh City 5
Mexico City 5
San Francisco 5
Vienna 5
Wilmington 5
Belo Horizonte 4
Catania 4
Johannesburg 4
Kitchener 4
Manchester 4
Querétaro 4
Bracknell 3
Buffalo 3
Curitiba 3
Dhaka 3
Dublin 3
Fiumicino 3
Genoa 3
Guangzhou 3
Hanoi 3
Hradec Králové 3
Leopoldshafen 3
Lissone 3
Maceió 3
Montegaldella 3
New Delhi 3
Orem 3
Palermo 3
Phoenix 3
Ribeirão Preto 3
Salvador 3
San José 3
Shenzhen 3
Vif 3
Ankara 2
Totale 3.519
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Nome #
Tritium in tokamak devices: Safety issues 294
Disruption prediction with artificial intelligence techniques in tokamak plasmas 271
Conceptual design studies for the European DEMO divertor: Rationale and first results 243
Rapporto preliminare del progetto del target di IFMIF comprensivo di disegni, analisi numeriche e valutazione dei costi 232
Eurofusion-DEMO Divertor - Cassette Design and Integration 230
Divertor of the European DEMO: Engineering and technologies for power exhaust 213
Tritium in tokamak devices: Technological issues 209
Integration of safety in IFMIF-DONES design 209
Large eddy simulation of Loss of Vacuum Accident in STARDUST facility 207
Design basis accident analysis for the Ignitor experiment 207
The European contribution to the development and validation activities for the design of IFMIF lithium facility 200
ECART analysis of the STARDUST dust resuspension tests with an obstacle presence 200
Exploratory fire analysis in DONES lithium system 200
Estimation of tritium and dust source term in european DEMOnstration fusion reactor during accident scenarios 196
Dust mobilization experiments in the context of the fusion plants - STARDUST facility 191
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 191
DEMO Divertor preliminary safety assessment 190
Analysis of an ex-vessel break in the ITER divertor cooling loop 190
Ex-vessel break in ITER divertor cooling loop analysis with the ECART code 189
ICE layer growth on a cryogenic surface in a fusion reactor during a loss of water event 188
The accomplishment of the Engineering Design Activities of IFMIF/EVEDA: The European-Japanese project towards a Li(d,xn) fusion relevant neutron source 187
Preliminary safety analysis of an in-vessel LOCA for the EU-DEMO WCLL blanket concept 187
Ingress of Coolant Event simulation with TRACE code with accuracy evaluation and coupled DAKOTA Uncertainty Analysis 184
Experimental and numerical analysis of the air inflow technique for dust removal from the vacuum vessel of a tokamak machine 183
DEMO – The main achievements of the Pre – Concept phase of the safety and environmental work package and the development of the GSSR 176
DEMO Divertor Cassette and Plasma facing Unit in Vessel Loss-of-Coolant Accident 171
Preliminary sensitivity analysis for an ex-vessel LOCA without plasma shutdown for the EU DEMO WCLL blanket concept 168
Supporting analysis for WCLL test blanket system safety 165
Modeling of a confinement bypass accident with CONSEN, a fast-running code for safety analyses in fusion reactors 163
Validation of the ECART code for the safety analysis of fusion reactors 159
Numerical study on Ingress of Coolant Event experiments with CONSEN code 156
Safety assessment for EU DEMO – Achievements and open issues in view of a generic site safety report 153
Tritium and dust source term inventory evaluation issues in the European DEMO reactor concepts 152
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 148
Totale 6.602
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Categoria #
all - tutte 27.672
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 27.672
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021149 0 0 0 0 0 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
2024/20252.863 12 108 50 56 138 53 99 136 128 99 863 1.121
2025/20262.002 323 581 591 291 187 29 0 0 0 0 0 0
Totale 6.602