statistiche ricercatore

MASCARI, FULVIO

Distribuzione geografica

Continente	#
EU - Europa	5.263
NA - Nord America	4.039
AS - Asia	2.137
SA - Sud America	295
AF - Africa	91
OC - Oceania	6
Continente sconosciuto - Info sul continente non disponibili	1
Totale	11.832

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Nazione	#
US - Stati Uniti d'America	3.900
RU - Federazione Russa	3.486
SG - Singapore	967
CN - Cina	665
IT - Italia	512
FR - Francia	338
BR - Brasile	260
DE - Germania	252
AT - Austria	175
GB - Regno Unito	164
HK - Hong Kong	127
SE - Svezia	126
JP - Giappone	113
CA - Canada	98
VN - Vietnam	73
KR - Corea	68
MA - Marocco	60
FI - Finlandia	48
IN - India	42
NL - Olanda	41
PL - Polonia	33
ES - Italia	22
MX - Messico	22
CZ - Repubblica Ceca	16
AR - Argentina	13
BD - Bangladesh	12
BE - Belgio	12
ZA - Sudafrica	11
UZ - Uzbekistan	10
TR - Turchia	9
IQ - Iraq	8
IE - Irlanda	7
LT - Lituania	7
PK - Pakistan	7
UA - Ucraina	7
IR - Iran	6
CO - Colombia	5
DZ - Algeria	5
EC - Ecuador	5
AE - Emirati Arabi Uniti	4
AU - Australia	4
ET - Etiopia	4
HU - Ungheria	4
JO - Giordania	4
CL - Cile	3
HN - Honduras	3
IL - Israele	3
JM - Giamaica	3
KZ - Kazakistan	3
PA - Panama	3
VE - Venezuela	3
BG - Bulgaria	2
BH - Bahrain	2
CH - Svizzera	2
DM - Dominica	2
GR - Grecia	2
GT - Guatemala	2
ID - Indonesia	2
KE - Kenya	2
LV - Lettonia	2
MY - Malesia	2
NI - Nicaragua	2
PT - Portogallo	2
PY - Paraguay	2
SA - Arabia Saudita	2
UY - Uruguay	2
AD - Andorra	1
BJ - Benin	1
CI - Costa d'Avorio	1
CR - Costa Rica	1
DO - Repubblica Dominicana	1
EG - Egitto	1
EU - Europa	1
GD - Grenada	1
GM - Gambi	1
GY - Guiana	1
KG - Kirghizistan	1
KW - Kuwait	1
LA - Repubblica Popolare Democratica del Laos	1
LB - Libano	1
LK - Sri Lanka	1
MZ - Mozambico	1
NG - Nigeria	1
NZ - Nuova Zelanda	1
PE - Perù	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
TN - Tunisia	1
TW - Taiwan	1
TZ - Tanzania	1
UG - Uganda	1
Totale	11.832

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Città	#
Dallas	2.242
Moscow	833
Singapore	432
Chandler	281
Ashburn	236
Hefei	203
Paris	148
Santa Clara	135
Rome	117
Beijing	114
Hong Kong	107
Vienna	98
Boardman	81
Toronto	77
New York	70
San Mateo	66
Seoul	66
Southend	64
Hamburg	63
Los Angeles	61
The Dalles	58
Casablanca	56
Nuremberg	50
Tokyo	43
Munich	31
Falkenstein	26
Milan	26
Warsaw	26
Berlin	25
São Paulo	25
Helsinki	24
Miami	24
North Bergen	24
Dong Ket	22
Council Bluffs	21
Ho Chi Minh City	19
Shenzhen	19
Stockholm	19
Bologna	18
Palermo	18
Amsterdam	17
Denver	16
Guangzhou	15
London	15
Marseille	15
Chennai	14
Xi'an	14
Chicago	13
Montreal	13
Redwood City	12
Turku	12
Frankfurt am Main	11
Houston	11
Rio de Janeiro	11
Atlanta	10
Brussels	10
Hanoi	10
Johannesburg	10
Manchester	10
Mexico City	10
Orem	10
Ann Arbor	9
Brooklyn	9
Charlotte	9
Columbus	9
Jülich	9
Lappeenranta	9
Tashkent	9
Turin	9
Belo Horizonte	8
Hangzhou	8
Mountain View	8
Poplar	8
San Francisco	8
Trenton	8
Las Vegas	7
Boston	6
Brno	6
Düsseldorf	6
Mumbai	6
Ningbo	6
Querétaro	6
Seattle	6
Shijiazhuang	6
Washington	6
Ankara	5
Naples	5
Uberlândia	5
Amman	4
Budapest	4
Buffalo	4
Cixi	4
Dhaka	4
Dublin	4
Pisa	4
Prague	4
Salvador	4
Shaoxing	4
Tappahannock	4
Tehran	4
Totale	6.571

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Nome	#
Severe accident sensitivity and uncertainty estimation using MELCOR and RAVEN	903
Summary of the activities and analyses carried out using USNRC codes in 2023	567
Divertor Tokamak Test facility project: status of design and implementation	387
Analyses with MELCOR code of an unmitigated SBO scenario with in vessel retention strategy applied to a generic PWR 900 MWe	278
Analisi delle temperature nei fondi dei generatori di vapore di reattori frontalieri PWR da 900 MWE in caso di LBLOCA in gamma calda	258
Description of PERSEO Test n. 7 for International Open Benchmark Exercise	235
In-containment source term predictability of ASTEC-Na: Major insights from data-predictions benchmarking	229
ASTEC - RAVEN coupling for uncertainty analysis of an ingress of coolant event in fusion plants	221
Description of PERSEO test n 7	219
Analysis of nodalization strategies to model a suppression tank for fusion plants with TRACE code	218
Implementazione su calcolatore parallelo di metodi e codici per le analisi di sensitività ed incertezza nel calcolo di incidenti severi	218
Analyses of an unmitigated station blackout transient with ASTEC, MAAP and MELCOR Codes	215
Analysis of a Station Black-Out transient in SMR by using the TRACE and RELAP5 code	213
Analyses of the TRACE V5 capability for the simulation of natural circulation and primary/containment coupling in BDBA condition typical of the MASLWR	213
ASTEC code DBA analysis of a passive mitigation strategy on a generic IRIS SMR	204
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	191
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	185
Ingress of Coolant Event simulation with TRACE code with accuracy evaluation and coupled DAKOTA Uncertainty Analysis	185
Analysis of BDBA sequences in a generic IRIS reactor using ASTEC code	179
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	178
Validation of the trace code against small modular integral reactor natural circulation phenomena	174
A Bayesian framework of inverse uncertainty quantification with principal component analysis and Kriging for the reliability analysis of passive safety systems	173
Analisi e valutazioni di incidenti severi in LWR	172
Qualification of RELAP5-3D Code Against the In-pool Passive Energy Removal System PERSEO Data	171
A systematic approach for the adequacy analysis of a set of experimental databases: Application in the framework of the ATRIUM activity	169
Scaling issues for the experimental characterization of reactor coolant system in integral test facilities and role of system code as extrapolation tool	169
Integral Calculations of Severe Accident Scenarios in PWRs and BWRs	165
Relazione sulle attività svolte e le analisi effettuate con i codici USNRC	163
Summary of the activities and analyses carried out using USNRC codes	162
Analysis of unmitigated large break loss of coolant accidents using MELCOR code	161
Analysis of an unmitigated 2-inch cold leg LOCA transient with ASTEC and MELCOR codes	158
Integral study of accident sequences with reference to NPPs next to the Italian borders	156
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	153
Current status of MELCOR 2.2 for fusion safety analyses	148
Summary of the activities and analyses carried out using USNRC CODES in 2022	148
Progress in modeling in-containment source term with ASTEC-Na	148
Analyses of the MELCOR Capability to Simulate Integral PWR Using Passive Systems	147
Adaptive Sampling Limit Surface Search Application to Identify Cliff-Edge Effects in Severe Accident Uncertainty Analysis	145
Analyses of design extension conditions without significant fuel degradation for operating nuclear power plants: An OECD/NEA review	140
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	139
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	139
BEPU analysis of an Upgraded ICE facility test by TRACE/DAKOTA coupling	137
Preliminary thermal-hydraulic deterministic safety analysis of an in-vessel LOCA for the DTT facility	132
Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project	132
MELCOR – DAKOTA coupling for uncertainty analyses in the SNAP environment/architecture	130
Qualification of RELAP5-3D code condensation model against full-scale PERSEO Test 9	124
Small modular reactors and insights on passive mitigation strategy modeling	123
OECD/NEA/CSNI/WGAMA PERSEO benchmark: Main outcomes and conclusions	123
Validation and uncertainty analysis of ASTEC in early degradation phase against QUENCH-06 experiment	122
Global Sensitivity Analysis for Segmented Inverse Uncertainty Quantification in the Safety Analysis of Nuclear Power Plants	118
Scaling-up assessment of natural circulation phenomena in integral Small Modular Reactor by TRACE code	118
Uncertainty and Sensitivity Analyses for Postulated Severe Accidents of Reference PWRs and SMRs in the Frame of the IAEA CRP and Relevant Insights	118
Nuclear safety Enhanced: A Deep dive into current and future RAVEN applications	117
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	117
Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: First outcomes	116
Passive safety systems analysis: A novel approach for inverse uncertainty quantification based on Stacked Sparse Autoencoders and Kriging metamodeling	116
ASTEC–MAAP Comparison of a 2 Inch Cold Leg LOCA until RPV Failure	115
Advances in Transient Thermal-Hydraulics in Water Cooled Nuclear Reactors: Main Outcomes of the OECD/NEA Specialist Meeting	115
Major Achievements of the EC MUSA Project	113
Simulation of QUENCH-06 Experiment by MELCOR v2.2 with Uncertainty Analysis	113
OECD/NEA/CSNI state-of-the-art report on scaling in system thermal-hydraulics applications to nuclear reactor safety and design (The S-SOAR)	112
The EC MUSA project on management and uncertainty of severe accidents: Main pillars and status	112
Uncertainty quantification for severe-accident reactor modelling: Results and conclusions of the MUSA reactor applications work package	108
Flow instabilities in helical-coil steam generators for small modular reactors: A review	107
BEPU analysis of a passive decay heat removal system with RELAP5/MOD3.3 and RELAP5-3D	104
Cold Leg LBLOCA uncertainty analysis using TRACE/DAKOTA coupling	104
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	102
SBO analysis of a generic PWR-900 with ASTEC and MELCOR codes	76
null	75
Totale	11.995

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Categoria	#
all - tutte	38.337
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	38.337

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2020/2021	175	0	0	0	0	0	4	8	25	11	18	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	4.722	556	1.242	1.805	660	288	171	0	0	0	0	0	0
Totale													11.995