statistiche ricercatore

PORFIRI, MARIA TERESA

Distribuzione geografica

Continente	#
NA - Nord America	988
EU - Europa	671
AS - Asia	208
Continente sconosciuto - Info sul continente non disponibili	4
OC - Oceania	1
Totale	1.872

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Nazione	#
US - Stati Uniti d'America	906
GB - Regno Unito	165
CN - Cina	140
SE - Svezia	131
IT - Italia	128
CA - Canada	82
FI - Finlandia	63
DE - Germania	57
FR - Francia	32
SG - Singapore	28
HK - Hong Kong	27
RU - Federazione Russa	27
BE - Belgio	21
NL - Olanda	9
ES - Italia	8
RO - Romania	8
GR - Grecia	7
CZ - Repubblica Ceca	6
IN - India	6
EU - Europa	4
PL - Polonia	3
UA - Ucraina	3
JP - Giappone	2
KZ - Kazakistan	2
VN - Vietnam	2
AT - Austria	1
CH - Svizzera	1
ID - Indonesia	1
IE - Irlanda	1
NZ - Nuova Zelanda	1
Totale	1.872

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Città	#
Chandler	342
Ashburn	86
Southend	84
Boardman	82
San Mateo	78
Toronto	67
New York	49
Lappeenranta	38
Beijing	33
Berlin	30
Hong Kong	26
Helsinki	25
Rome	23
Brussels	21
Miami	19
Singapore	17
Trenton	14
Falls Church	9
Los Angeles	9
Marseille	9
Redwood City	8
Las Vegas	7
Ottawa	7
Raleigh	7
Washington	7
Madrid	6
Mountain View	6
Veniano	6
Ann Arbor	5
Dongguan	5
Milan	5
Munich	5
Wilmington	5
Kitchener	4
Shanghai	4
Bracknell	3
Fiumicino	3
Hradec Králové	3
Leopoldshafen	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
Piaseczno	2
Redmond	2
Rockville	2
San Francesco al Campo	2
Stendal	2
Torino	2
Amsterdam	1
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
Nuremberg	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
Vienna	1
Totale	1.245

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Nome	#
Tritium in tokamak devices: Safety issues	141
Preliminary safety analysis of an in-vessel LOCA for the EU-DEMO WCLL blanket concept	90
Estimation of tritium and dust source term in european DEMOnstration fusion reactor during accident scenarios	75
Design basis accident analysis for the Ignitor experiment	71
Conceptual design studies for the European DEMO divertor: Rationale and first results	68
Rapporto preliminare del progetto del target di IFMIF comprensivo di disegni, analisi numeriche e valutazione dei costi	66
Integration of safety in IFMIF-DONES design	66
Eurofusion-DEMO Divertor - Cassette Design and Integration	65
Tritium in tokamak devices: Technological issues	62
Preliminary sensitivity analysis for an ex-vessel LOCA without plasma shutdown for the EU DEMO WCLL blanket concept	62
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	62
The accomplishment of the Engineering Design Activities of IFMIF/EVEDA: The European-Japanese project towards a Li(d,xn) fusion relevant neutron source	61
Tritium and dust source term inventory evaluation issues in the European DEMO reactor concepts	61
ICE layer growth on a cryogenic surface in a fusion reactor during a loss of water event	60
The European contribution to the development and validation activities for the design of IFMIF lithium facility	60
Analysis of an ex-vessel break in the ITER divertor cooling loop	59
Ex-vessel break in ITER divertor cooling loop analysis with the ECART code	59
Exploratory fire analysis in DONES lithium system	59
Large eddy simulation of Loss of Vacuum Accident in STARDUST facility	58
Dust mobilization experiments in the context of the fusion plants - STARDUST facility	57
ECART analysis of the STARDUST dust resuspension tests with an obstacle presence	56
Modeling of a confinement bypass accident with CONSEN, a fast-running code for safety analyses in fusion reactors	54
Numerical study on Ingress of Coolant Event experiments with CONSEN code	52
Experimental and numerical analysis of the air inflow technique for dust removal from the vacuum vessel of a tokamak machine	50
Validation of the ECART code for the safety analysis of fusion reactors	49
Ingress of Coolant Event simulation with TRACE code with accuracy evaluation and coupled DAKOTA Uncertainty Analysis	49
Safety assessment for EU DEMO – Achievements and open issues in view of a generic site safety report	47
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	45
Supporting analysis for WCLL test blanket system safety	42
DEMO Divertor preliminary safety assessment	39
DEMO Divertor Cassette and Plasma facing Unit in Vessel Loss-of-Coolant Accident	34
Divertor of the European DEMO: Engineering and technologies for power exhaust	25
DEMO – The main achievements of the Pre – Concept phase of the safety and environmental work package and the development of the GSSR	18
Totale	1.922

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Categoria	#
all - tutte	14.157
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	14.157

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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	185	12	108	50	15	0	0	0	0	0	0	0	0
Totale													1.922