PORFIRI, MARIA TERESA
 Distribuzione geografica
Continente #
NA - Nord America 781
EU - Europa 581
AS - Asia 29
Continente sconosciuto - Info sul continente non disponibili 4
OC - Oceania 1
Totale 1.396
Nazione #
US - Stati Uniti d'America 699
GB - Regno Unito 165
SE - Svezia 131
IT - Italia 93
CA - Canada 82
DE - Germania 51
BE - Belgio 50
FI - Finlandia 26
FR - Francia 19
CN - Cina 15
AT - Austria 10
NL - Olanda 8
RO - Romania 8
GR - Grecia 6
IN - India 6
CZ - Repubblica Ceca 5
EU - Europa 4
ES - Italia 3
UA - Ucraina 3
JP - Giappone 2
KZ - Kazakistan 2
VN - Vietnam 2
CH - Svizzera 1
HK - Hong Kong 1
ID - Indonesia 1
NZ - Nuova Zelanda 1
PL - Polonia 1
RU - Federazione Russa 1
Totale 1.396
Città #
Chandler 342
Southend 84
San Mateo 78
Toronto 67
Brussels 50
Boardman 31
Ashburn 30
Berlin 30
Helsinki 25
Rome 18
Vienna 10
Falls Church 9
Redwood City 8
Las Vegas 7
Miami 7
Ottawa 7
Raleigh 7
Mountain View 6
Veniano 6
Ann Arbor 5
Wilmington 5
Kitchener 4
Bracknell 3
Fiumicino 3
Hradec Králové 3
Leopoldshafen 3
Madrid 3
Milan 3
Montegaldella 3
Arlington 2
Atyrau 2
Bangalore 2
Dong Ket 2
Kralupy nad Vltavou 2
Lincoln 2
Monfalcone 2
Nepean 2
Palermo 2
Redmond 2
Rockville 2
San Francesco al Campo 2
Stendal 2
Torino 2
Auckland 1
Borås 1
Boydton 1
Bracciano 1
Buffalo 1
Canale Monterano 1
Council Bluffs 1
Florence 1
Fort McMurray 1
Fremont 1
Gif-sur-yvette 1
Groningen 1
Horia 1
Huizen 1
Ibra 1
Jakarta Pusat 1
Lappeenranta 1
London 1
Monza 1
Muravera 1
Nanjing 1
Neptune City 1
Parabiago 1
Philadelphia 1
Pinerolo 1
Piove Di Sacco 1
Pisa 1
Pistoia 1
Polska 1
Ragusa 1
Reggio Emilia 1
Saskatoon 1
Swadlincote 1
Tappahannock 1
Virginia Beach 1
Xian 1
Zurich 1
Totale 922
Nome #
Tritium in tokamak devices: Safety issues 115
Preliminary safety analysis of an in-vessel LOCA for the EU-DEMO WCLL blanket concept 72
Rapporto preliminare del progetto del target di IFMIF comprensivo di disegni, analisi numeriche e valutazione dei costi 56
Estimation of tritium and dust source term in european DEMOnstration fusion reactor during accident scenarios 55
Tritium and dust source term inventory evaluation issues in the European DEMO reactor concepts 54
Analysis of an ex-vessel break in the ITER divertor cooling loop 51
Conceptual design studies for the European DEMO divertor: Rationale and first results 51
Integration of safety in IFMIF-DONES design 51
The accomplishment of the Engineering Design Activities of IFMIF/EVEDA: The European-Japanese project towards a Li(d,xn) fusion relevant neutron source 49
Tritium in tokamak devices: Technological issues 49
Eurofusion-DEMO Divertor - Cassette Design and Integration 49
The European contribution to the development and validation activities for the design of IFMIF lithium facility 48
Ex-vessel break in ITER divertor cooling loop analysis with the ECART code 47
Design basis accident analysis for the Ignitor experiment 47
Exploratory fire analysis in DONES lithium system 47
ECART analysis of the STARDUST dust resuspension tests with an obstacle presence 44
Modeling of a confinement bypass accident with CONSEN, a fast-running code for safety analyses in fusion reactors 43
ICE layer growth on a cryogenic surface in a fusion reactor during a loss of water event 43
Numerical study on Ingress of Coolant Event experiments with CONSEN code 42
Ingress of Coolant Event simulation with TRACE code with accuracy evaluation and coupled DAKOTA Uncertainty Analysis 42
Dust mobilization experiments in the context of the fusion plants - STARDUST facility 41
Preliminary sensitivity analysis for an ex-vessel LOCA without plasma shutdown for the EU DEMO WCLL blanket concept 41
Validation of the ECART code for the safety analysis of fusion reactors 40
Large eddy simulation of Loss of Vacuum Accident in STARDUST facility 39
Safety assessment for EU DEMO – Achievements and open issues in view of a generic site safety report 39
Experimental and numerical analysis of the air inflow technique for dust removal from the vacuum vessel of a tokamak machine 38
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 34
Supporting analysis for WCLL test blanket system safety 30
DEMO Divertor preliminary safety assessment 25
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 25
DEMO Divertor Cassette and Plasma facing Unit in Vessel Loss-of-Coolant Accident 22
Divertor of the European DEMO: Engineering and technologies for power exhaust 10
DEMO – The main achievements of the Pre – Concept phase of the safety and environmental work package and the development of the GSSR 3
Totale 1.442
Categoria #
all - tutte 9.162
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 9.162


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/202023 0 0 0 0 0 4 3 2 0 12 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
2022/2023662 54 125 55 92 23 120 16 45 88 18 7 19
2023/2024189 29 18 52 33 47 10 0 0 0 0 0 0
Totale 1.442