statistiche ricercatore

MASCARI, FULVIO

Distribuzione geografica

Continente	#
EU - Europa	5.593
NA - Nord America	5.139
AS - Asia	2.567
SA - Sud America	360
Continente sconosciuto - Info sul continente non disponibili	172
AF - Africa	106
OC - Oceania	10
Totale	13.947

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Nazione	#
US - Stati Uniti d'America	4.971
RU - Federazione Russa	3.445
SG - Singapore	1.105
CN - Cina	759
IT - Italia	581
FR - Francia	522
BR - Brasile	297
DE - Germania	265
GB - Regno Unito	179
SE - Svezia	178
AT - Austria	176
VN - Vietnam	156
HK - Hong Kong	146
JP - Giappone	117
CA - Canada	110
KR - Corea	68
MA - Marocco	62
IN - India	57
NL - Olanda	51
FI - Finlandia	49
BD - Bangladesh	44
PL - Polonia	36
ES - Italia	31
MX - Messico	29
AR - Argentina	19
CZ - Repubblica Ceca	15
IQ - Iraq	15
TR - Turchia	14
ZA - Sudafrica	13
BE - Belgio	12
PK - Pakistan	12
UZ - Uzbekistan	12
LT - Lituania	11
UA - Ucraina	10
CO - Colombia	9
EC - Ecuador	9
AU - Australia	8
CL - Cile	8
MY - Malesia	8
IE - Irlanda	7
IR - Iran	6
JO - Giordania	6
VE - Venezuela	6
AE - Emirati Arabi Uniti	5
DZ - Algeria	5
ET - Etiopia	5
HU - Ungheria	5
ID - Indonesia	5
IL - Israele	5
JM - Giamaica	5
CR - Costa Rica	4
NI - Nicaragua	4
PH - Filippine	4
PT - Portogallo	4
SA - Arabia Saudita	4
TN - Tunisia	4
UY - Uruguay	4
BO - Bolivia	3
EG - Egitto	3
GT - Guatemala	3
HN - Honduras	3
KE - Kenya	3
KG - Kirghizistan	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
KH - Cambogia	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
PS - Palestinian Territory	1
SI - Slovenia	1
Totale	13.768

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Città	#
Dallas	2.241
Moscow	819
San Jose	483
Singapore	475
Ashburn	359
Chandler	281
Paris	258
Council Bluffs	218
Hefei	202
Santa Clara	145
Hong Kong	126
Rome	120
Beijing	116
Vienna	99
The Dalles	88
Boardman	82
New York	82
Toronto	79
Los Angeles	75
San Mateo	66
Seoul	66
Southend	64
Hamburg	63
Casablanca	57
Lauterbourg	56
Nuremberg	51
Ho Chi Minh City	48
Tokyo	46
Chicago	34
Orem	34
Hanoi	33
Munich	31
São Paulo	30
Warsaw	28
Falkenstein	27
Milan	27
Berlin	25
Bologna	25
Helsinki	24
Miami	24
North Bergen	24
Amsterdam	22
Dong Ket	22
London	19
Shenzhen	19
Stockholm	19
Denver	18
Palermo	18
Chennai	17
Marseille	17
Guangzhou	15
Frankfurt am Main	14
Hillsboro	14
Montreal	14
Phoenix	14
Xi'an	14
Manchester	13
Atlanta	12
Brooklyn	12
Mexico City	12
Redwood City	12
Rio de Janeiro	12
Turku	12
Houston	11
Johannesburg	11
Tashkent	11
Turin	11
Brussels	10
Charlotte	10
Lappeenranta	10
Ann Arbor	9
Belo Horizonte	9
Columbus	9
Jülich	9
Hangzhou	8
Mountain View	8
Poplar	8
San Francisco	8
Trenton	8
Ankara	7
Buffalo	7
Las Vegas	7
Mumbai	7
Amman	6
Boston	6
Brno	6
Dhaka	6
Düsseldorf	6
Haiphong	6
Naples	6
Ningbo	6
Querétaro	6
Seattle	6
Shijiazhuang	6
Washington	6
Budapest	5
Da Nang	5
Guayaquil	5
Uberlândia	5
Addis Ababa	4
Totale	7.846

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Nome	#
Severe accident sensitivity and uncertainty estimation using MELCOR and RAVEN	934
Summary of the activities and analyses carried out using USNRC codes in 2023	604
Divertor Tokamak Test facility project: status of design and implementation	432
Analyses with MELCOR code of an unmitigated SBO scenario with in vessel retention strategy applied to a generic PWR 900 MWe	321
Analisi delle temperature nei fondi dei generatori di vapore di reattori frontalieri PWR da 900 MWE in caso di LBLOCA in gamma calda	290
Description of PERSEO Test n. 7 for International Open Benchmark Exercise	271
ASTEC - RAVEN coupling for uncertainty analysis of an ingress of coolant event in fusion plants	260
Description of PERSEO test n 7	258
In-containment source term predictability of ASTEC-Na: Major insights from data-predictions benchmarking	254
Analysis of a Station Black-Out transient in SMR by using the TRACE and RELAP5 code	249
Analysis of nodalization strategies to model a suppression tank for fusion plants with TRACE code	247
Analyses of the TRACE V5 capability for the simulation of natural circulation and primary/containment coupling in BDBA condition typical of the MASLWR	247
Implementazione su calcolatore parallelo di metodi e codici per le analisi di sensitività ed incertezza nel calcolo di incidenti severi	241
Analyses of an unmitigated station blackout transient with ASTEC, MAAP and MELCOR Codes	240
ASTEC code DBA analysis of a passive mitigation strategy on a generic IRIS SMR	237
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	232
Ingress of Coolant Event simulation with TRACE code with accuracy evaluation and coupled DAKOTA Uncertainty Analysis	219
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	216
Analysis of BDBA sequences in a generic IRIS reactor using ASTEC code	214
A systematic approach for the adequacy analysis of a set of experimental databases: Application in the framework of the ATRIUM activity	207
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	206
A Bayesian framework of inverse uncertainty quantification with principal component analysis and Kriging for the reliability analysis of passive safety systems	205
Analysis of unmitigated large break loss of coolant accidents using MELCOR code	204
Scaling issues for the experimental characterization of reactor coolant system in integral test facilities and role of system code as extrapolation tool	200
Analisi e valutazioni di incidenti severi in LWR	200
Qualification of RELAP5-3D Code Against the In-pool Passive Energy Removal System PERSEO Data	194
Validation of the trace code against small modular integral reactor natural circulation phenomena	194
Integral Calculations of Severe Accident Scenarios in PWRs and BWRs	192
Relazione sulle attività svolte e le analisi effettuate con i codici USNRC	190
Current status of MELCOR 2.2 for fusion safety analyses	189
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	184
Analysis of an unmitigated 2-inch cold leg LOCA transient with ASTEC and MELCOR codes	183
Analyses of design extension conditions without significant fuel degradation for operating nuclear power plants: An OECD/NEA review	182
Integral study of accident sequences with reference to NPPs next to the Italian borders	182
Summary of the activities and analyses carried out using USNRC CODES in 2022	181
Summary of the activities and analyses carried out using USNRC codes	178
Analyses of the MELCOR Capability to Simulate Integral PWR Using Passive Systems	176
Progress in modeling in-containment source term with ASTEC-Na	174
Adaptive Sampling Limit Surface Search Application to Identify Cliff-Edge Effects in Severe Accident Uncertainty Analysis	169
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	169
BEPU analysis of an Upgraded ICE facility test by TRACE/DAKOTA coupling	163
Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project	162
Passive safety systems analysis: A novel approach for inverse uncertainty quantification based on Stacked Sparse Autoencoders and Kriging metamodeling	161
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	159
OECD/NEA/CSNI/WGAMA PERSEO benchmark: Main outcomes and conclusions	158
Scaling-up assessment of natural circulation phenomena in integral Small Modular Reactor by TRACE code	157
MELCOR – DAKOTA coupling for uncertainty analyses in the SNAP environment/architecture	157
Preliminary thermal-hydraulic deterministic safety analysis of an in-vessel LOCA for the DTT facility	154
Validation and uncertainty analysis of ASTEC in early degradation phase against QUENCH-06 experiment	153
Uncertainty quantification for severe-accident reactor modelling: Results and conclusions of the MUSA reactor applications work package	149
OECD/NEA/CSNI state-of-the-art report on scaling in system thermal-hydraulics applications to nuclear reactor safety and design (The S-SOAR)	149
Small modular reactors and insights on passive mitigation strategy modeling	149
Global Sensitivity Analysis for Segmented Inverse Uncertainty Quantification in the Safety Analysis of Nuclear Power Plants	146
ASTEC–MAAP Comparison of a 2 Inch Cold Leg LOCA until RPV Failure	146
Nuclear safety Enhanced: A Deep dive into current and future RAVEN applications	145
Qualification of RELAP5-3D code condensation model against full-scale PERSEO Test 9	145
Advances in Transient Thermal-Hydraulics in Water Cooled Nuclear Reactors: Main Outcomes of the OECD/NEA Specialist Meeting	144
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	144
Uncertainty and Sensitivity Analyses for Postulated Severe Accidents of Reference PWRs and SMRs in the Frame of the IAEA CRP and Relevant Insights	143
Major Achievements of the EC MUSA Project	139
Simulation of QUENCH-06 Experiment by MELCOR v2.2 with Uncertainty Analysis	139
Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: First outcomes	137
Flow instabilities in helical-coil steam generators for small modular reactors: A review	129
The EC MUSA project on management and uncertainty of severe accidents: Main pillars and status	126
Cold Leg LBLOCA uncertainty analysis using TRACE/DAKOTA coupling	122
BEPU analysis of a passive decay heat removal system with RELAP5/MOD3.3 and RELAP5-3D	116
SBO analysis of a generic PWR-900 with ASTEC and MELCOR codes	95
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	82
An empirical method for inverse uncertainty quantification in nuclear thermal–hydraulic codes	46
Uncertainty quantification application on the Phebus FPT1 using the coupling of MELCOR and DAKOTA in a Python environment/architecture	6
Analyses of the MELCOR capability to simulate integral PWR using passive systems in a DBA scenario	1
Totale	13.947

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Categoria	#
all - tutte	45.066
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	45.066

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2021/2022	303	0	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	5.391	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	178	53	125	0	0	0	0	0	0	0	0	0	0
Totale													13.947