statistiche ricercatore

PORFIRI, MARIA TERESA

Distribuzione geografica

Continente	#
NA - Nord America	955
EU - Europa	655
AS - Asia	149
Continente sconosciuto - Info sul continente non disponibili	4
OC - Oceania	1
Totale	1.764

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Nazione	#
US - Stati Uniti d'America	873
GB - Regno Unito	165
SE - Svezia	131
IT - Italia	121
CN - Cina	95
CA - Canada	82
FI - Finlandia	63
DE - Germania	56
FR - Francia	31
HK - Hong Kong	27
RU - Federazione Russa	27
BE - Belgio	21
SG - Singapore	14
NL - Olanda	8
RO - Romania	8
GR - Grecia	7
CZ - Repubblica Ceca	6
IN - India	6
ES - Italia	5
EU - Europa	4
UA - Ucraina	3
JP - Giappone	2
KZ - Kazakistan	2
VN - Vietnam	2
CH - Svizzera	1
ID - Indonesia	1
IE - Irlanda	1
NZ - Nuova Zelanda	1
PL - Polonia	1
Totale	1.764

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Città	#
Chandler	342
Ashburn	86
Southend	84
San Mateo	78
Toronto	67
Boardman	49
New York	49
Lappeenranta	38
Berlin	30
Beijing	26
Hong Kong	26
Helsinki	25
Brussels	21
Rome	21
Miami	19
Trenton	14
Falls Church	9
Los Angeles	9
Marseille	9
Redwood City	8
Singapore	8
Las Vegas	7
Ottawa	7
Raleigh	7
Washington	7
Mountain View	6
Veniano	6
Ann Arbor	5
Dongguan	5
Milan	5
Munich	5
Wilmington	5
Kitchener	4
Bracknell	3
Fiumicino	3
Hradec Králové	3
Leopoldshafen	3
Madrid	3
Montegaldella	3
Palermo	3
Pisa	3
Arlington	2
Atyrau	2
Bangalore	2
Cagliari	2
Dong Ket	2
Granada	2
Kralupy nad Vltavou	2
Lincoln	2
Livorno	2
Monfalcone	2
Naples	2
Nepean	2
Redmond	2
Rockville	2
San Francesco al Campo	2
Shanghai	2
Stendal	2
Torino	2
Auckland	1
Bollate	1
Borås	1
Bracciano	1
Brno	1
Buffalo	1
Canale Monterano	1
Council Bluffs	1
Dublin	1
Florence	1
Fort McMurray	1
Gif-sur-yvette	1
Groningen	1
Guangzhou	1
Horia	1
Huizen	1
Ibra	1
Jakarta Pusat	1
London	1
Monza	1
Muravera	1
Nanjing	1
Neptune City	1
Ovada	1
Parabiago	1
Paris	1
Philadelphia	1
Pinerolo	1
Piove Di Sacco	1
Pistoia	1
Polska	1
Ragusa	1
Reggio Emilia	1
Santa Clara	1
Saskatoon	1
Swadlincote	1
Tappahannock	1
Virginia Beach	1
Xian	1
Zurich	1
Totale	1.187

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Nome	#
Tritium in tokamak devices: Safety issues	129
Preliminary safety analysis of an in-vessel LOCA for the EU-DEMO WCLL blanket concept	84
Design basis accident analysis for the Ignitor experiment	68
Estimation of tritium and dust source term in european DEMOnstration fusion reactor during accident scenarios	66
Conceptual design studies for the European DEMO divertor: Rationale and first results	65
Rapporto preliminare del progetto del target di IFMIF comprensivo di disegni, analisi numeriche e valutazione dei costi	64
Integration of safety in IFMIF-DONES design	63
Eurofusion-DEMO Divertor - Cassette Design and Integration	62
Tritium and dust source term inventory evaluation issues in the European DEMO reactor concepts	60
Preliminary sensitivity analysis for an ex-vessel LOCA without plasma shutdown for the EU DEMO WCLL blanket concept	60
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	60
The European contribution to the development and validation activities for the design of IFMIF lithium facility	59
Ex-vessel break in ITER divertor cooling loop analysis with the ECART code	57
Tritium in tokamak devices: Technological issues	57
Exploratory fire analysis in DONES lithium system	57
Analysis of an ex-vessel break in the ITER divertor cooling loop	56
The accomplishment of the Engineering Design Activities of IFMIF/EVEDA: The European-Japanese project towards a Li(d,xn) fusion relevant neutron source	56
Large eddy simulation of Loss of Vacuum Accident in STARDUST facility	56
Dust mobilization experiments in the context of the fusion plants - STARDUST facility	54
ECART analysis of the STARDUST dust resuspension tests with an obstacle presence	54
ICE layer growth on a cryogenic surface in a fusion reactor during a loss of water event	53
Modeling of a confinement bypass accident with CONSEN, a fast-running code for safety analyses in fusion reactors	51
Numerical study on Ingress of Coolant Event experiments with CONSEN code	50
Experimental and numerical analysis of the air inflow technique for dust removal from the vacuum vessel of a tokamak machine	48
Validation of the ECART code for the safety analysis of fusion reactors	47
Ingress of Coolant Event simulation with TRACE code with accuracy evaluation and coupled DAKOTA Uncertainty Analysis	46
Safety assessment for EU DEMO – Achievements and open issues in view of a generic site safety report	45
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	44
Supporting analysis for WCLL test blanket system safety	41
DEMO Divertor preliminary safety assessment	36
DEMO Divertor Cassette and Plasma facing Unit in Vessel Loss-of-Coolant Accident	32
Divertor of the European DEMO: Engineering and technologies for power exhaust	23
DEMO – The main achievements of the Pre – Concept phase of the safety and environmental work package and the development of the GSSR	9
Totale	1.812

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Categoria	#
all - tutte	13.388
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	13.388

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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	638	54	125	55	92	23	120	11	42	85	14	6	11
2023/2024	508	22	16	50	25	47	97	15	62	44	40	27	63
2024/2025	75	12	63	0	0	0	0	0	0	0	0	0	0
Totale													1.812