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 #
NA - Nord America 3.228
EU - Europa 3.016
AS - Asia 1.441
SA - Sud America 254
Continente sconosciuto - Info sul continente non disponibili 60
AF - Africa 49
OC - Oceania 5
Totale 8.053
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Nazione #
US - Stati Uniti d'America 3.088
RU - Federazione Russa 1.890
SG - Singapore 642
CN - Cina 433
IT - Italia 230
GB - Regno Unito 220
BR - Brasile 212
SE - Svezia 168
DE - Germania 133
FR - Francia 132
CA - Canada 107
VN - Vietnam 90
FI - Finlandia 79
HK - Hong Kong 75
JP - Giappone 49
KR - Corea 37
NL - Olanda 33
IN - India 30
MA - Marocco 29
BE - Belgio 24
PL - Polonia 24
BD - Bangladesh 22
MX - Messico 19
ES - Italia 15
AT - Austria 11
EC - Ecuador 11
RO - Romania 9
AR - Argentina 8
CZ - Repubblica Ceca 8
IQ - Iraq 8
LT - Lituania 8
TR - Turchia 8
GR - Grecia 7
VE - Venezuela 7
ZA - Sudafrica 7
ID - Indonesia 6
UA - Ucraina 6
CO - Colombia 5
CR - Costa Rica 5
KZ - Kazakistan 5
CL - Cile 4
EU - Europa 4
KE - Kenya 4
SA - Arabia Saudita 4
TH - Thailandia 4
AU - Australia 3
IE - Irlanda 3
KG - Kirghizistan 3
MY - Malesia 3
PH - Filippine 3
PK - Pakistan 3
AL - Albania 2
BN - Brunei Darussalam 2
BO - Bolivia 2
CH - Svizzera 2
CI - Costa d'Avorio 2
CY - Cipro 2
DZ - Algeria 2
EE - Estonia 2
JM - Giamaica 2
NP - Nepal 2
NZ - Nuova Zelanda 2
PE - Perù 2
PT - Portogallo 2
PY - Paraguay 2
RS - Serbia 2
TN - Tunisia 2
UZ - Uzbekistan 2
AE - Emirati Arabi Uniti 1
AM - Armenia 1
AZ - Azerbaigian 1
BB - Barbados 1
BG - Bulgaria 1
BY - Bielorussia 1
CU - Cuba 1
DM - Dominica 1
DO - Repubblica Dominicana 1
EG - Egitto 1
ET - Etiopia 1
HU - Ungheria 1
JO - Giordania 1
LB - Libano 1
LU - Lussemburgo 1
LV - Lettonia 1
NI - Nicaragua 1
OM - Oman 1
SD - Sudan 1
SK - Slovacchia (Repubblica Slovacca) 1
SV - El Salvador 1
SY - Repubblica araba siriana 1
TT - Trinidad e Tobago 1
TW - Taiwan 1
UY - Uruguay 1
Totale 7.997
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Città #
Dallas 762
Moscow 415
Chandler 342
Singapore 296
San Jose 295
Ashburn 266
Council Bluffs 167
Santa Clara 119
Hefei 103
New York 88
Beijing 85
Southend 84
Boardman 82
The Dalles 81
San Mateo 78
Hong Kong 73
Toronto 69
Los Angeles 52
Lappeenranta 41
Phoenix 36
Rome 36
Seoul 35
Berlin 30
Lauterbourg 29
Helsinki 28
Ho Chi Minh City 27
Columbus 26
Munich 26
Aix-en-Provence 24
Brussels 23
Miami 23
Nuremberg 23
Casablanca 22
Milan 21
Orem 18
São Paulo 18
Hanoi 17
Warsaw 17
Amsterdam 16
London 15
Trenton 14
Paris 13
Chennai 12
Tokyo 12
Boston 11
Chicago 11
Montreal 11
Brooklyn 10
Frankfurt am Main 10
Las Vegas 10
Falls Church 9
Marseille 9
Poplar 9
Shanghai 9
Washington 9
Atlanta 8
Falkenstein 8
Ottawa 8
Redwood City 8
Rio de Janeiro 8
Stockholm 8
Turku 8
Buffalo 7
Denver 7
Hillsboro 7
Houston 7
Madrid 7
North Tonawanda 7
Raleigh 7
San Francisco 7
Karlsruhe 6
Manheim 6
Mountain View 6
Pisa 6
Veniano 6
Ann Arbor 5
Belo Horizonte 5
Dongguan 5
Harvard 5
Johannesburg 5
Manchester 5
Mexico City 5
Nonantola 5
Querétaro 5
San José 5
Vienna 5
Wilmington 5
Brasília 4
Catania 4
Curitiba 4
Da Nang 4
Guayaquil 4
Haiphong 4
Kitchener 4
Nairobi 4
Naples 4
New Delhi 4
Philadelphia 4
Vilnius 4
Ankara 3
Totale 4.420
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Nome #
Tritium in tokamak devices: Safety issues 363
Disruption prediction with artificial intelligence techniques in tokamak plasmas 324
Conceptual design studies for the European DEMO divertor: Rationale and first results 290
Divertor of the European DEMO: Engineering and technologies for power exhaust 282
Eurofusion-DEMO Divertor - Cassette Design and Integration 272
Rapporto preliminare del progetto del target di IFMIF comprensivo di disegni, analisi numeriche e valutazione dei costi 270
Design basis accident analysis for the Ignitor experiment 262
Integration of safety in IFMIF-DONES design 255
Estimation of tritium and dust source term in european DEMOnstration fusion reactor during accident scenarios 251
ECART analysis of the STARDUST dust resuspension tests with an obstacle presence 249
Large eddy simulation of Loss of Vacuum Accident in STARDUST facility 245
Tritium in tokamak devices: Technological issues 244
The European contribution to the development and validation activities for the design of IFMIF lithium facility 242
Analysis of an ex-vessel break in the ITER divertor cooling loop 238
Exploratory fire analysis in DONES lithium system 237
DEMO Divertor preliminary safety assessment 236
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 234
Dust mobilization experiments in the context of the fusion plants - STARDUST facility 226
ICE layer growth on a cryogenic surface in a fusion reactor during a loss of water event 225
Ingress of Coolant Event simulation with TRACE code with accuracy evaluation and coupled DAKOTA Uncertainty Analysis 225
Experimental and numerical analysis of the air inflow technique for dust removal from the vacuum vessel of a tokamak machine 224
Ex-vessel break in ITER divertor cooling loop analysis with the ECART code 222
DEMO Divertor Cassette and Plasma facing Unit in Vessel Loss-of-Coolant Accident 221
The accomplishment of the Engineering Design Activities of IFMIF/EVEDA: The European-Japanese project towards a Li(d,xn) fusion relevant neutron source 221
DEMO – The main achievements of the Pre – Concept phase of the safety and environmental work package and the development of the GSSR 220
Modeling of a confinement bypass accident with CONSEN, a fast-running code for safety analyses in fusion reactors 213
Preliminary safety analysis of an in-vessel LOCA for the EU-DEMO WCLL blanket concept 211
Supporting analysis for WCLL test blanket system safety 204
Numerical study on Ingress of Coolant Event experiments with CONSEN code 199
Preliminary sensitivity analysis for an ex-vessel LOCA without plasma shutdown for the EU DEMO WCLL blanket concept 196
Validation of the ECART code for the safety analysis of fusion reactors 195
Tritium and dust source term inventory evaluation issues in the European DEMO reactor concepts 193
Safety assessment for EU DEMO – Achievements and open issues in view of a generic site safety report 184
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 180
Totale 8.053
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Categoria #
all - tutte 32.553
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 32.553
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2021/2022275 0 0 0 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
2025/20262.996 323 581 591 291 187 175 336 181 78 127 108 18
2026/2027457 30 124 160 143 0 0 0 0 0 0 0 0
Totale 8.053