statistiche ricercatore

MASCARI, FULVIO

Distribuzione geografica

Continente	#
EU - Europa	5.572
NA - Nord America	4.867
AS - Asia	2.524
SA - Sud America	362
AF - Africa	106
OC - Oceania	10
Continente sconosciuto - Info sul continente non disponibili	1
Totale	13.442

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Nazione	#
US - Stati Uniti d'America	4.717
RU - Federazione Russa	3.495
SG - Singapore	1.116
CN - Cina	742
IT - Italia	564
FR - Francia	524
BR - Brasile	301
DE - Germania	266
GB - Regno Unito	177
AT - Austria	176
VN - Vietnam	157
HK - Hong Kong	143
SE - Svezia	129
JP - Giappone	115
CA - Canada	103
KR - Corea	68
MA - Marocco	62
IN - India	59
FI - Finlandia	49
NL - Olanda	48
PL - Polonia	37
ES - Italia	30
MX - Messico	28
AR - Argentina	20
BD - Bangladesh	17
CZ - Repubblica Ceca	16
IQ - Iraq	15
TR - Turchia	15
ZA - Sudafrica	13
BE - Belgio	12
PK - Pakistan	12
UZ - Uzbekistan	12
LT - Lituania	10
CO - Colombia	9
UA - Ucraina	9
AU - Australia	8
CL - Cile	8
EC - Ecuador	8
IE - Irlanda	7
IR - Iran	6
JO - Giordania	6
MY - Malesia	6
VE - Venezuela	6
DZ - Algeria	5
ET - Etiopia	5
HU - Ungheria	5
IL - Israele	5
AE - Emirati Arabi Uniti	4
ID - Indonesia	4
PT - Portogallo	4
TN - Tunisia	4
EG - Egitto	3
HN - Honduras	3
JM - Giamaica	3
KE - Kenya	3
KG - Kirghizistan	3
KZ - Kazakistan	3
PA - Panama	3
PH - Filippine	3
SA - Arabia Saudita	3
UY - Uruguay	3
BG - Bulgaria	2
BH - Bahrain	2
BO - Bolivia	2
CH - Svizzera	2
CI - Costa d'Avorio	2
DM - Dominica	2
GR - Grecia	2
GT - Guatemala	2
LV - Lettonia	2
NI - Nicaragua	2
PE - Perù	2
PY - Paraguay	2
AD - Andorra	1
AL - Albania	1
AO - Angola	1
BJ - Benin	1
BY - Bielorussia	1
CR - Costa Rica	1
DK - Danimarca	1
DO - Repubblica Dominicana	1
EU - Europa	1
GD - Grenada	1
GM - Gambi	1
GY - Guiana	1
KW - Kuwait	1
LA - Repubblica Popolare Democratica del Laos	1
LB - Libano	1
LK - Sri Lanka	1
LY - Libia	1
MZ - Mozambico	1
NG - Nigeria	1
NP - Nepal	1
NZ - Nuova Zelanda	1
PG - Papua Nuova Guinea	1
PS - Palestinian Territory	1
SI - Slovenia	1
SK - Slovacchia (Repubblica Slovacca)	1
SV - El Salvador	1
TH - Thailandia	1
Totale	13.438

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Città	#
Dallas	2.243
Moscow	833
San Jose	478
Singapore	476
Ashburn	355
Chandler	281
Paris	258
Hefei	203
Santa Clara	135
Rome	126
Hong Kong	123
Beijing	115
Vienna	99
The Dalles	88
Boardman	82
Toronto	78
New York	73
Los Angeles	68
Council Bluffs	66
San Mateo	66
Seoul	66
Southend	64
Hamburg	63
Casablanca	57
Lauterbourg	56
Nuremberg	51
Ho Chi Minh City	48
Tokyo	45
Orem	34
Hanoi	33
Chicago	31
Munich	31
São Paulo	31
Milan	29
Warsaw	28
Falkenstein	27
Berlin	25
Helsinki	24
Miami	24
North Bergen	24
Amsterdam	22
Dong Ket	22
Bologna	19
Denver	19
Shenzhen	19
Stockholm	19
Chennai	18
London	18
Marseille	18
Palermo	18
Frankfurt am Main	15
Guangzhou	15
Hillsboro	15
Xi'an	14
Manchester	13
Montreal	13
Brooklyn	12
Redwood City	12
Rio de Janeiro	12
Turku	12
Atlanta	11
Houston	11
Johannesburg	11
Mexico City	11
Tashkent	11
Turin	11
Brussels	10
Charlotte	10
Columbus	10
Lappeenranta	10
Ann Arbor	9
Belo Horizonte	9
Jülich	9
Hangzhou	8
Mountain View	8
Poplar	8
San Francisco	8
Trenton	8
Ankara	7
Las Vegas	7
Mumbai	7
Amman	6
Boston	6
Brno	6
Buffalo	6
Düsseldorf	6
Haiphong	6
Ningbo	6
Querétaro	6
Seattle	6
Shijiazhuang	6
Washington	6
Budapest	5
Da Nang	5
Dhaka	5
Naples	5
Phoenix	5
Uberlândia	5
Addis Ababa	4
Biên Hòa	4
Totale	7.660

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Nome	#
Severe accident sensitivity and uncertainty estimation using MELCOR and RAVEN	925
Summary of the activities and analyses carried out using USNRC codes in 2023	598
Divertor Tokamak Test facility project: status of design and implementation	424
Analyses with MELCOR code of an unmitigated SBO scenario with in vessel retention strategy applied to a generic PWR 900 MWe	309
Analisi delle temperature nei fondi dei generatori di vapore di reattori frontalieri PWR da 900 MWE in caso di LBLOCA in gamma calda	282
Description of PERSEO Test n. 7 for International Open Benchmark Exercise	262
ASTEC - RAVEN coupling for uncertainty analysis of an ingress of coolant event in fusion plants	249
In-containment source term predictability of ASTEC-Na: Major insights from data-predictions benchmarking	249
Description of PERSEO test n 7	247
Analysis of a Station Black-Out transient in SMR by using the TRACE and RELAP5 code	244
Analysis of nodalization strategies to model a suppression tank for fusion plants with TRACE code	238
Implementazione su calcolatore parallelo di metodi e codici per le analisi di sensitività ed incertezza nel calcolo di incidenti severi	238
Analyses of the TRACE V5 capability for the simulation of natural circulation and primary/containment coupling in BDBA condition typical of the MASLWR	235
Analyses of an unmitigated station blackout transient with ASTEC, MAAP and MELCOR Codes	233
ASTEC code DBA analysis of a passive mitigation strategy on a generic IRIS SMR	230
Fukushima Dai-ichi Unit 1 Accident Simulation by Best Estimate and Integral Codes & Accident Management Procedures Identification Focusing on BWR close to the Italian Borders	221
Ingress of Coolant Event simulation with TRACE code with accuracy evaluation and coupled DAKOTA Uncertainty Analysis	215
Analisi mediante il codice TRACE delle principali fenomenologie caratterizzanti il transitorio conseguente ad una rottura a ghigliottina nella linea DVI dell’impianto sperimentale SPES-3	209
Analysis of BDBA sequences in a generic IRIS reactor using ASTEC code	204
A Bayesian framework of inverse uncertainty quantification with principal component analysis and Kriging for the reliability analysis of passive safety systems	200
Analisi di transitori non mitigati: perdite di refrigerante da piccola rottura in PWR, perdita d’acqua di alimento del GV in PWR e SBO in BWR	200
A systematic approach for the adequacy analysis of a set of experimental databases: Application in the framework of the ATRIUM activity	196
Scaling issues for the experimental characterization of reactor coolant system in integral test facilities and role of system code as extrapolation tool	196
Analysis of unmitigated large break loss of coolant accidents using MELCOR code	195
Analisi e valutazioni di incidenti severi in LWR	194
Validation of the trace code against small modular integral reactor natural circulation phenomena	192
Qualification of RELAP5-3D Code Against the In-pool Passive Energy Removal System PERSEO Data	188
Integral Calculations of Severe Accident Scenarios in PWRs and BWRs	187
Current status of MELCOR 2.2 for fusion safety analyses	182
Relazione sulle attività svolte e le analisi effettuate con i codici USNRC	182
Application of REPAS to analyze the sump clogging issue following a LOCA and its impact on the reliability of the ECCS long-term core cooling function	180
Integral study of accident sequences with reference to NPPs next to the Italian borders	179
Analysis of an unmitigated 2-inch cold leg LOCA transient with ASTEC and MELCOR codes	178
Summary of the activities and analyses carried out using USNRC codes	177
Analyses of the MELCOR Capability to Simulate Integral PWR Using Passive Systems	170
Summary of the activities and analyses carried out using USNRC CODES in 2022	169
Progress in modeling in-containment source term with ASTEC-Na	169
Analyses of design extension conditions without significant fuel degradation for operating nuclear power plants: An OECD/NEA review	166
Modifiche del codice RELAP5/MOD3.2.β per lo studio delle perdite di carico e dello scambio termico in condotti elicoidali interessati da deflussi bifase: Validazione attraverso gli esperimenti effettuati dalPolitecnico di Milano presso l’impianto SIET di Piacenza	166
Adaptive Sampling Limit Surface Search Application to Identify Cliff-Edge Effects in Severe Accident Uncertainty Analysis	164
BEPU analysis of an Upgraded ICE facility test by TRACE/DAKOTA coupling	159
Nodalizzazione MELCOR per lo Studio Integrale di Sequenze Incidentali su Reattori PWR da 900 MWe e valutazioni preliminari d’impatto a breve e medio raggio	158
Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project	156
Preliminary thermal-hydraulic deterministic safety analysis of an in-vessel LOCA for the DTT facility	151
MELCOR – DAKOTA coupling for uncertainty analyses in the SNAP environment/architecture	151
OECD/NEA/CSNI/WGAMA PERSEO benchmark: Main outcomes and conclusions	147
Scaling-up assessment of natural circulation phenomena in integral Small Modular Reactor by TRACE code	146
Validation and uncertainty analysis of ASTEC in early degradation phase against QUENCH-06 experiment	146
Small modular reactors and insights on passive mitigation strategy modeling	143
Qualification of RELAP5-3D code condensation model against full-scale PERSEO Test 9	143
ASTEC–MAAP Comparison of a 2 Inch Cold Leg LOCA until RPV Failure	142
Evaluations of radionuclide activity releases into environment during loss of coolant accidents using the ASTEC code in pressurized water reactors within design basis and design extension conditions	141
Passive safety systems analysis: A novel approach for inverse uncertainty quantification based on Stacked Sparse Autoencoders and Kriging metamodeling	141
Global Sensitivity Analysis for Segmented Inverse Uncertainty Quantification in the Safety Analysis of Nuclear Power Plants	140
OECD/NEA/CSNI state-of-the-art report on scaling in system thermal-hydraulics applications to nuclear reactor safety and design (The S-SOAR)	140
Nuclear safety Enhanced: A Deep dive into current and future RAVEN applications	139
Uncertainty quantification for severe-accident reactor modelling: Results and conclusions of the MUSA reactor applications work package	138
Uncertainty and Sensitivity Analyses for Postulated Severe Accidents of Reference PWRs and SMRs in the Frame of the IAEA CRP and Relevant Insights	138
Advances in Transient Thermal-Hydraulics in Water Cooled Nuclear Reactors: Main Outcomes of the OECD/NEA Specialist Meeting	135
Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: First outcomes	134
Major Achievements of the EC MUSA Project	134
Simulation of QUENCH-06 Experiment by MELCOR v2.2 with Uncertainty Analysis	130
Flow instabilities in helical-coil steam generators for small modular reactors: A review	128
The EC MUSA project on management and uncertainty of severe accidents: Main pillars and status	123
Cold Leg LBLOCA uncertainty analysis using TRACE/DAKOTA coupling	122
Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool	119
BEPU analysis of a passive decay heat removal system with RELAP5/MOD3.3 and RELAP5-3D	115
SBO analysis of a generic PWR-900 with ASTEC and MELCOR codes	92
null	76
An empirical method for inverse uncertainty quantification in nuclear thermal–hydraulic codes	40
Totale	13.609

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Categoria	#
all - tutte	41.552
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	41.552

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2020/2021	109	0	0	0	0	0	0	0	0	0	0	78	31
2021/2022	309	6	72	13	18	22	5	30	57	11	6	35	34
2022/2023	737	52	137	39	92	37	127	14	86	109	20	12	12
2023/2024	469	29	12	49	16	47	73	35	35	25	22	55	71
2024/2025	5.457	19	141	25	68	162	25	139	483	390	281	1.556	2.168
2025/2026	6.336	556	1.242	1.805	660	288	321	578	371	213	281	21	0
Totale													13.609