statistiche ricercatore

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

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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

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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

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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

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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

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2019/2020	23	0	0	0	0	0	4	3	2	0	12	0	2
2020/2021	198	1	0	0	3	45	0	6	26	8	15	85	9
2021/2022	370	8	84	3	36	39	9	20	82	27	6	26	30
2022/2023	662	54	125	55	92	23	120	16	45	88	18	7	19
2023/2024	189	29	18	52	33	47	10	0	0	0	0	0	0
Totale													1.442