statistiche ricercatore

MASCARI, FULVIO

Distribuzione geografica

Continente	#
EU - Europa	5.713
NA - Nord America	5.712
AS - Asia	2.588
SA - Sud America	385
Continente sconosciuto - Info sul continente non disponibili	174
AF - Africa	107
OC - Oceania	10
Totale	14.689

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Nazione	#
US - Stati Uniti d'America	5.514
RU - Federazione Russa	3.445
SG - Singapore	1.106
CN - Cina	759
IT - Italia	665
FR - Francia	528
BR - Brasile	305
DE - Germania	266
GB - Regno Unito	196
SE - Svezia	180
AT - Austria	177
VN - Vietnam	157
HK - Hong Kong	150
CA - Canada	124
JP - Giappone	118
KR - Corea	71
MA - Marocco	62
IN - India	57
NL - Olanda	53
FI - Finlandia	49
BD - Bangladesh	46
PL - Polonia	36
ES - Italia	31
MX - Messico	31
AR - Argentina	22
CO - Colombia	17
BE - Belgio	15
CZ - Repubblica Ceca	15
IQ - Iraq	15
TR - Turchia	14
ZA - Sudafrica	13
PK - Pakistan	12
UZ - Uzbekistan	12
LT - Lituania	11
EC - Ecuador	10
UA - Ucraina	10
VE - Venezuela	10
CL - Cile	9
MY - Malesia	9
AU - Australia	8
GT - Guatemala	7
ID - Indonesia	7
IE - Irlanda	7
AE - Emirati Arabi Uniti	6
CR - Costa Rica	6
IR - Iran	6
JO - Giordania	6
NI - Nicaragua	6
PH - Filippine	6
DZ - Algeria	5
ET - Etiopia	5
HN - Honduras	5
HU - Ungheria	5
IL - Israele	5
JM - Giamaica	5
PT - Portogallo	5
SA - Arabia Saudita	5
SV - El Salvador	4
TN - Tunisia	4
UY - Uruguay	4
BO - Bolivia	3
EE - Estonia	3
EG - Egitto	3
KE - Kenya	3
KG - Kirghizistan	3
KH - Cambogia	3
KZ - Kazakistan	3
PA - Panama	3
BG - Bulgaria	2
BH - Bahrain	2
CH - Svizzera	2
CI - Costa d'Avorio	2
DM - Dominica	2
GR - Grecia	2
IS - Islanda	2
LA - Repubblica Popolare Democratica del Laos	2
LV - Lettonia	2
PE - Perù	2
PY - Paraguay	2
TW - Taiwan	2
AD - Andorra	1
AL - Albania	1
AO - Angola	1
BJ - Benin	1
BY - Bielorussia	1
DK - Danimarca	1
DO - Repubblica Dominicana	1
EU - Europa	1
GD - Grenada	1
GM - Gambi	1
GY - Guiana	1
KW - Kuwait	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
Totale	14.505

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Città	#
Dallas	2.247
Moscow	819
San Jose	484
Singapore	475
Ashburn	399
Council Bluffs	360
Chandler	281
Paris	259
Hefei	202
Santa Clara	153
Rome	131
Hong Kong	130
Beijing	116
Vienna	100
New York	90
The Dalles	88
Los Angeles	83
Boardman	82
Toronto	80
San Mateo	66
Seoul	66
Southend	64
Hamburg	63
North Bergen	62
Casablanca	57
Lauterbourg	56
Nuremberg	51
Phoenix	49
Ho Chi Minh City	48
Tokyo	46
Chicago	37
Orem	35
Hanoi	34
Milan	33
Munich	31
São Paulo	31
Warsaw	28
Falkenstein	27
Berlin	26
Bologna	26
Miami	26
Helsinki	24
Amsterdam	22
Dong Ket	22
Stockholm	20
London	19
Shenzhen	19
Denver	18
Palermo	18
Chennai	17
Marseille	17
Montreal	17
North Tonawanda	17
Brooklyn	15
Guangzhou	15
Hillsboro	15
Atlanta	14
Frankfurt am Main	14
Houston	14
Xi'an	14
Manchester	13
Turin	13
Mexico City	12
Redwood City	12
Rio de Janeiro	12
Turku	12
Johannesburg	11
Naples	11
Tashkent	11
Brussels	10
Charlotte	10
Lappeenranta	10
San Francisco	10
Ann Arbor	9
Belo Horizonte	9
Columbus	9
Jülich	9
Las Vegas	9
Hangzhou	8
Mountain View	8
Poplar	8
Trenton	8
Washington	8
Ankara	7
Buffalo	7
Mumbai	7
Seattle	7
Amman	6
Bogotá	6
Boston	6
Brno	6
Dhaka	6
Düsseldorf	6
Haiphong	6
Managua	6
Ningbo	6
Pisa	6
Querétaro	6
Shijiazhuang	6
Brasília	5
Totale	8.209

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Nome	#
Severe accident sensitivity and uncertainty estimation using MELCOR and RAVEN	943
Summary of the activities and analyses carried out using USNRC codes in 2023	618
Divertor Tokamak Test facility project: status of design and implementation	453
Analyses with MELCOR code of an unmitigated SBO scenario with in vessel retention strategy applied to a generic PWR 900 MWe	335
Analisi delle temperature nei fondi dei generatori di vapore di reattori frontalieri PWR da 900 MWE in caso di LBLOCA in gamma calda	299
Description of PERSEO Test n. 7 for International Open Benchmark Exercise	280
ASTEC - RAVEN coupling for uncertainty analysis of an ingress of coolant event in fusion plants	271
Description of PERSEO test n 7	270
In-containment source term predictability of ASTEC-Na: Major insights from data-predictions benchmarking	263
Analysis of a Station Black-Out transient in SMR by using the TRACE and RELAP5 code	259
Analysis of nodalization strategies to model a suppression tank for fusion plants with TRACE code	258
Analyses of the TRACE V5 capability for the simulation of natural circulation and primary/containment coupling in BDBA condition typical of the MASLWR	257
Implementazione su calcolatore parallelo di metodi e codici per le analisi di sensitività ed incertezza nel calcolo di incidenti severi	255
Analyses of an unmitigated station blackout transient with ASTEC, MAAP and MELCOR Codes	248
ASTEC code DBA analysis of a passive mitigation strategy on a generic IRIS SMR	241
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	241
Analysis of BDBA sequences in a generic IRIS reactor using ASTEC code	228
Ingress of Coolant Event simulation with TRACE code with accuracy evaluation and coupled DAKOTA Uncertainty Analysis	227
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	222
Analysis of unmitigated large break loss of coolant accidents using MELCOR code	218
Scaling issues for the experimental characterization of reactor coolant system in integral test facilities and role of system code as extrapolation tool	217
A systematic approach for the adequacy analysis of a set of experimental databases: Application in the framework of the ATRIUM activity	216
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	216
A Bayesian framework of inverse uncertainty quantification with principal component analysis and Kriging for the reliability analysis of passive safety systems	211
Analisi e valutazioni di incidenti severi in LWR	210
Validation of the trace code against small modular integral reactor natural circulation phenomena	209
Qualification of RELAP5-3D Code Against the In-pool Passive Energy Removal System PERSEO Data	208
Integral Calculations of Severe Accident Scenarios in PWRs and BWRs	207
Current status of MELCOR 2.2 for fusion safety analyses	202
Analyses of design extension conditions without significant fuel degradation for operating nuclear power plants: An OECD/NEA review	200
Analysis of an unmitigated 2-inch cold leg LOCA transient with ASTEC and MELCOR codes	199
Relazione sulle attività svolte e le analisi effettuate con i codici USNRC	195
Integral study of accident sequences with reference to NPPs next to the Italian borders	191
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	189
Progress in modeling in-containment source term with ASTEC-Na	187
Summary of the activities and analyses carried out using USNRC codes	187
Summary of the activities and analyses carried out using USNRC CODES in 2022	186
Analyses of the MELCOR Capability to Simulate Integral PWR Using Passive Systems	183
Adaptive Sampling Limit Surface Search Application to Identify Cliff-Edge Effects in Severe Accident Uncertainty Analysis	179
BEPU analysis of an Upgraded ICE facility test by TRACE/DAKOTA coupling	177
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	177
OECD/NEA/CSNI/WGAMA PERSEO benchmark: Main outcomes and conclusions	173
Passive safety systems analysis: A novel approach for inverse uncertainty quantification based on Stacked Sparse Autoencoders and Kriging metamodeling	170
Scaling-up assessment of natural circulation phenomena in integral Small Modular Reactor by TRACE code	169
Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project	169
Preliminary thermal-hydraulic deterministic safety analysis of an in-vessel LOCA for the DTT facility	167
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	166
Advances in Transient Thermal-Hydraulics in Water Cooled Nuclear Reactors: Main Outcomes of the OECD/NEA Specialist Meeting	164
MELCOR – DAKOTA coupling for uncertainty analyses in the SNAP environment/architecture	164
Uncertainty quantification for severe-accident reactor modelling: Results and conclusions of the MUSA reactor applications work package	159
OECD/NEA/CSNI state-of-the-art report on scaling in system thermal-hydraulics applications to nuclear reactor safety and design (The S-SOAR)	159
ASTEC–MAAP Comparison of a 2 Inch Cold Leg LOCA until RPV Failure	158
Small modular reactors and insights on passive mitigation strategy modeling	158
Validation and uncertainty analysis of ASTEC in early degradation phase against QUENCH-06 experiment	158
Global Sensitivity Analysis for Segmented Inverse Uncertainty Quantification in the Safety Analysis of Nuclear Power Plants	156
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	154
Simulation of QUENCH-06 Experiment by MELCOR v2.2 with Uncertainty Analysis	153
Nuclear safety Enhanced: A Deep dive into current and future RAVEN applications	152
Qualification of RELAP5-3D code condensation model against full-scale PERSEO Test 9	150
Major Achievements of the EC MUSA Project	149
Uncertainty and Sensitivity Analyses for Postulated Severe Accidents of Reference PWRs and SMRs in the Frame of the IAEA CRP and Relevant Insights	149
Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: First outcomes	146
Flow instabilities in helical-coil steam generators for small modular reactors: A review	133
The EC MUSA project on management and uncertainty of severe accidents: Main pillars and status	129
Cold Leg LBLOCA uncertainty analysis using TRACE/DAKOTA coupling	129
BEPU analysis of a passive decay heat removal system with RELAP5/MOD3.3 and RELAP5-3D	126
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	99
SBO analysis of a generic PWR-900 with ASTEC and MELCOR codes	98
An empirical method for inverse uncertainty quantification in nuclear thermal–hydraulic codes	62
Uncertainty quantification application on the Phebus FPT1 using the coupling of MELCOR and DAKOTA in a Python environment/architecture	25
Analyses of the MELCOR capability to simulate integral PWR using passive systems in a DBA scenario	13
Totale	14.689

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Categoria	#
all - tutte	47.796
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	47.796

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2021/2022	218	0	0	0	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	5.391	19	141	25	68	162	25	139	482	382	273	1.535	2.140
2025/2026	6.562	546	1.236	1.797	654	283	318	573	366	210	279	218	82
2026/2027	920	53	180	299	388	0	0	0	0	0	0	0	0
Totale													14.689