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 2.949
NA - Nord America 2.846
AS - Asia 1.422
SA - Sud America 231
AF - Africa 47
OC - Oceania 5
Continente sconosciuto - Info sul continente non disponibili 4
Totale 7.504
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Nazione #
US - Stati Uniti d'America 2.722
RU - Federazione Russa 1.890
SG - Singapore 638
CN - Cina 431
GB - Regno Unito 211
IT - Italia 209
BR - Brasile 201
SE - Svezia 151
DE - Germania 131
FR - Francia 128
CA - Canada 99
VN - Vietnam 86
FI - Finlandia 79
HK - Hong Kong 74
JP - Giappone 49
KR - Corea 36
NL - Olanda 31
IN - India 30
MA - Marocco 29
PL - Polonia 24
BE - Belgio 23
BD - Bangladesh 19
MX - Messico 17
ES - Italia 13
AT - Austria 11
RO - Romania 9
CZ - Repubblica Ceca 8
IQ - Iraq 8
TR - Turchia 8
GR - Grecia 7
ZA - Sudafrica 7
AR - Argentina 6
EC - Ecuador 6
ID - Indonesia 6
UA - Ucraina 6
KZ - Kazakistan 5
CL - Cile 4
EU - Europa 4
LT - Lituania 4
SA - Arabia Saudita 4
VE - Venezuela 4
AU - Australia 3
CO - Colombia 3
CR - Costa Rica 3
IE - Irlanda 3
KE - Kenya 3
KG - Kirghizistan 3
MY - Malesia 3
PK - Pakistan 3
BN - Brunei Darussalam 2
BO - Bolivia 2
CH - Svizzera 2
CI - Costa d'Avorio 2
CY - Cipro 2
NP - Nepal 2
NZ - Nuova Zelanda 2
PE - Perù 2
PH - Filippine 2
PT - Portogallo 2
PY - Paraguay 2
TN - Tunisia 2
UZ - Uzbekistan 2
AE - Emirati Arabi Uniti 1
AL - Albania 1
AM - Armenia 1
AZ - Azerbaigian 1
BB - Barbados 1
BY - Bielorussia 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
LV - Lettonia 1
OM - Oman 1
RS - Serbia 1
SD - Sudan 1
SK - Slovacchia (Repubblica Slovacca) 1
SY - Repubblica araba siriana 1
TH - Thailandia 1
TW - Taiwan 1
UY - Uruguay 1
Totale 7.504
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Città #
Dallas 755
Moscow 415
Chandler 342
Singapore 293
San Jose 291
Ashburn 248
Santa Clara 112
Hefei 103
Beijing 85
Southend 84
Boardman 82
New York 81
The Dalles 80
San Mateo 78
Hong Kong 73
Toronto 69
Council Bluffs 63
Lappeenranta 41
Los Angeles 39
Seoul 35
Rome 32
Berlin 30
Lauterbourg 29
Helsinki 28
Columbus 26
Munich 26
Aix-en-Provence 24
Ho Chi Minh City 24
Brussels 23
Nuremberg 23
Casablanca 22
Miami 20
Milan 19
Orem 17
São Paulo 17
Warsaw 17
Amsterdam 16
Hanoi 16
London 15
Trenton 14
Paris 13
Chennai 12
Tokyo 12
Montreal 11
Boston 10
Frankfurt am Main 10
Brooklyn 9
Falls Church 9
Marseille 9
Poplar 9
Falkenstein 8
Las Vegas 8
Ottawa 8
Redwood City 8
Shanghai 8
Stockholm 8
Turku 8
Atlanta 7
Chicago 7
Hillsboro 7
Madrid 7
Raleigh 7
Washington 7
Buffalo 6
Denver 6
Houston 6
Karlsruhe 6
Mountain View 6
Pisa 6
Rio de Janeiro 6
San Francisco 6
Veniano 6
Ann Arbor 5
Belo Horizonte 5
Dongguan 5
Johannesburg 5
Manchester 5
Mexico City 5
Nonantola 5
Querétaro 5
Vienna 5
Wilmington 5
Catania 4
Da Nang 4
Haiphong 4
Kitchener 4
New Delhi 4
Phoenix 4
Ankara 3
Baghdad 3
Bracknell 3
Curitiba 3
Dhaka 3
Dublin 3
Fiumicino 3
Genoa 3
Guangzhou 3
Hradec Králové 3
Hải Dương 3
Leopoldshafen 3
Totale 4.173
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Nome #
Tritium in tokamak devices: Safety issues 331
Disruption prediction with artificial intelligence techniques in tokamak plasmas 306
Conceptual design studies for the European DEMO divertor: Rationale and first results 273
Eurofusion-DEMO Divertor - Cassette Design and Integration 261
Rapporto preliminare del progetto del target di IFMIF comprensivo di disegni, analisi numeriche e valutazione dei costi 259
Divertor of the European DEMO: Engineering and technologies for power exhaust 252
Design basis accident analysis for the Ignitor experiment 242
Integration of safety in IFMIF-DONES design 239
Large eddy simulation of Loss of Vacuum Accident in STARDUST facility 234
Tritium in tokamak devices: Technological issues 234
ECART analysis of the STARDUST dust resuspension tests with an obstacle presence 232
Estimation of tritium and dust source term in european DEMOnstration fusion reactor during accident scenarios 227
Exploratory fire analysis in DONES lithium system 227
The European contribution to the development and validation activities for the design of IFMIF lithium facility 226
DEMO Divertor preliminary safety assessment 222
Analysis of an ex-vessel break in the ITER divertor cooling loop 222
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 217
Ingress of Coolant Event simulation with TRACE code with accuracy evaluation and coupled DAKOTA Uncertainty Analysis 216
Dust mobilization experiments in the context of the fusion plants - STARDUST facility 214
ICE layer growth on a cryogenic surface in a fusion reactor during a loss of water event 214
Experimental and numerical analysis of the air inflow technique for dust removal from the vacuum vessel of a tokamak machine 211
Ex-vessel break in ITER divertor cooling loop analysis with the ECART code 210
DEMO Divertor Cassette and Plasma facing Unit in Vessel Loss-of-Coolant Accident 208
The accomplishment of the Engineering Design Activities of IFMIF/EVEDA: The European-Japanese project towards a Li(d,xn) fusion relevant neutron source 207
DEMO – The main achievements of the Pre – Concept phase of the safety and environmental work package and the development of the GSSR 205
Preliminary safety analysis of an in-vessel LOCA for the EU-DEMO WCLL blanket concept 203
Modeling of a confinement bypass accident with CONSEN, a fast-running code for safety analyses in fusion reactors 196
Supporting analysis for WCLL test blanket system safety 193
Preliminary sensitivity analysis for an ex-vessel LOCA without plasma shutdown for the EU DEMO WCLL blanket concept 187
Numerical study on Ingress of Coolant Event experiments with CONSEN code 185
Validation of the ECART code for the safety analysis of fusion reactors 181
Tritium and dust source term inventory evaluation issues in the European DEMO reactor concepts 181
Safety assessment for EU DEMO – Achievements and open issues in view of a generic site safety report 175
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 170
Totale 7.560
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Categoria #
all - tutte 29.894
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 29.894
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/202194 0 0 0 0 0 0 0 0 0 0 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
2025/20262.960 323 581 591 291 187 175 336 181 78 127 90 0
Totale 7.560