statistiche ricercatore

EDERLI, STEFANO

Distribuzione geografica

Continente	#
EU - Europa	4.409
NA - Nord America	3.893
AS - Asia	2.287
SA - Sud America	328
AF - Africa	72
Continente sconosciuto - Info sul continente non disponibili	11
OC - Oceania	9
Totale	11.009

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Nazione	#
US - Stati Uniti d'America	3.689
RU - Federazione Russa	2.828
SG - Singapore	1.082
CN - Cina	568
DE - Germania	473
GB - Regno Unito	316
BR - Brasile	279
HK - Hong Kong	258
SE - Svezia	229
IT - Italia	213
CA - Canada	176
FR - Francia	158
VN - Vietnam	93
JP - Giappone	79
KR - Corea	63
IN - India	49
AT - Austria	39
MA - Marocco	38
FI - Finlandia	31
PL - Polonia	25
BE - Belgio	18
NL - Olanda	18
ES - Italia	17
MX - Messico	17
BD - Bangladesh	16
IQ - Iraq	16
AR - Argentina	15
TR - Turchia	13
EU - Europa	11
ZA - Sudafrica	9
AU - Australia	8
CO - Colombia	8
CZ - Repubblica Ceca	8
UZ - Uzbekistan	8
DZ - Algeria	7
LT - Lituania	7
TN - Tunisia	7
EC - Ecuador	6
IR - Iran	6
PK - Pakistan	6
UA - Ucraina	6
VE - Venezuela	6
MY - Malesia	5
CL - Cile	4
PY - Paraguay	4
SA - Arabia Saudita	4
GR - Grecia	3
HU - Ungheria	3
ID - Indonesia	3
KZ - Kazakistan	3
PH - Filippine	3
PT - Portogallo	3
AL - Albania	2
BB - Barbados	2
BO - Bolivia	2
CR - Costa Rica	2
DO - Repubblica Dominicana	2
EG - Egitto	2
ET - Etiopia	2
IL - Israele	2
NO - Norvegia	2
RO - Romania	2
RS - Serbia	2
UY - Uruguay	2
AZ - Azerbaigian	1
BH - Bahrain	1
BW - Botswana	1
CI - Costa d'Avorio	1
CY - Cipro	1
EE - Estonia	1
GA - Gabon	1
GE - Georgia	1
GH - Ghana	1
GT - Guatemala	1
GY - Guiana	1
HN - Honduras	1
IE - Irlanda	1
JM - Giamaica	1
JO - Giordania	1
KE - Kenya	1
KG - Kirghizistan	1
LB - Libano	1
LK - Sri Lanka	1
LV - Lettonia	1
LY - Libia	1
MK - Macedonia	1
MQ - Martinica	1
NP - Nepal	1
NZ - Nuova Zelanda	1
OM - Oman	1
PA - Panama	1
PE - Perù	1
SI - Slovenia	1
SK - Slovacchia (Repubblica Slovacca)	1
ZW - Zimbabwe	1
Totale	11.009

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Città	#
Dallas	971
Moscow	670
Chandler	506
Singapore	483
San Jose	402
Ashburn	287
Hamburg	261
Santa Clara	184
Hefei	171
Toronto	155
Southend	153
San Mateo	151
Hong Kong	142
Boardman	129
New York	115
Beijing	110
Council Bluffs	79
The Dalles	67
Seoul	59
Rome	54
Berlin	53
Lauterbourg	53
Los Angeles	47
Casablanca	35
Munich	34
Ho Chi Minh City	32
Hanoi	27
Orem	27
Falkenstein	26
Columbus	25
Nuremberg	25
Vienna	25
Las Vegas	24
Marseille	24
Paris	24
São Paulo	24
Ann Arbor	23
Warsaw	23
Washington	21
Helsinki	20
Bologna	19
Brussels	18
Tokyo	18
Trenton	18
Miami	16
Belo Horizonte	15
Frankfurt am Main	15
Mountain View	14
Redwood City	14
Guangzhou	13
Manchester	13
Palermo	12
Tong	12
Rio de Janeiro	11
Chicago	10
London	10
Poplar	10
Shanghai	10
Chennai	9
Jülich	9
Montreal	9
Phoenix	9
Turku	9
Amsterdam	8
Atlanta	8
Tashkent	8
Boston	7
Brooklyn	7
Dong Ket	7
Mumbai	7
Baghdad	6
Buffalo	6
Charlotte	6
Curitiba	6
Gif-sur-yvette	6
Mazzano Romano	6
Milan	6
Brno	5
Guayaquil	5
Johannesburg	5
Limburg an der Lahn	5
Querétaro	5
San Francisco	5
Shenzhen	5
Stockholm	5
Wilmington	5
Borås	4
Brasília	4
Denver	4
Düsseldorf	4
Eagleville	4
Haiphong	4
Houston	4
Istanbul	4
Juiz de Fora	4
North Bergen	4
Redmond	4
Rockville	4
San Vito Lo Capo	4
Seattle	4
Totale	6.229

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Nome	#
Assessment of ASTEC-Na Thermal-Hydraulic Models on Experiments and Benchmarking with Other Codes	456
Analysis of ASTEC-Na capabilities for simulating a loss of flow CABRI experiment	440
Calcoli e validazioni relativi ai codici di calcolo specifici per l’analisi degli incidenti gravi	319
Analyses with MELCOR code of an unmitigated SBO scenario with in vessel retention strategy applied to a generic PWR 900 MWe	313
Analysis of B9+ PHEBUS SFD Experiment with ICARE2 and SCDAP/RELAP 5 Codes	291
Analysis of the ZrO2 Layer Chemical Stability in Zry Cladding above Zry Melting Point. Definition and Validation of a ZrO2 Failure Criterion to be Implemented in the Core Degradation Codes	267
Analysis of SCARABEE BE+3 experiment with ASTEC-Na and comparison with other SFR safety analysis codes	253
ENEA activity in CESAM Project	250
Development and Verification of Calculation Models for the Accident Analysis in Nuclear Power Plants	250
ASTEC code DBA analysis of a passive mitigation strategy on a generic IRIS SMR	235
Assessment of PWR cores behavior and estimate of confidence level got with the use of mechanistic and / or integral codes calculations of accident sequences with reference to TMI-2 reactor	233
DRACCAR code validation against the ballooned cluster experiment A2R038 of the ACHILLES experimental program	223
DRACCAR code validation against unballooned cluster ACHILLES experiments	213
Analysis of BDBA sequences in a generic IRIS reactor using ASTEC code	211
ENEA Activities in the First 6 Months of 1998	210
ENEA-PISA University Contribution to the Reinforced Concerted Action Final Report Core Degradation. Core Severe Damage Modeling	210
Calculs complémentaires DRACCAR-2 en soutien à la préparation des essais TAGINE sur le réacteur BR2	205
Single and two-phase sodium flow analysis for two tucop cabri tests using the ASTEC-Na code	201
Investigation of Core Degradation (COBE). Final Report	194
ENEA Activities in the Last 6 Months of 1998	193
Synthesis of spent fuel pool accident assessments using severe accident codes	190
PHEBUS FPT3: Preliminary Investigation for Designing a Bundle with a B4C Rod	186
Analysis of PBF SFD 1-4 TEST with ICARE2 V2 Mod1 code. Application of a New Criterion for the Cladding External Layer Failure beyond the Zircaloy Melting	184
Analysis of an unmitigated 2-inch cold leg LOCA transient with ASTEC and MELCOR codes	182
Exploratory ICARE 2 Calculations for the PHEBUS FPT2 Test (Bundle Aspect)	180
ICARE V3 Mod0 Code Validation against MP-1 Experiment	176
Synthesis of the current understanding of the PHEBUS FP FPT2 test based on the ICARE2 code calculations	169
ICARE2 V3 Mod0 Validation against DC1 Experiment	168
PHEBUS FPT4. First Post Test Calculation on the Debris Bed Using the ICARE2 V3 Code	167
Investigation of Core Degradation (COBE)	167
Post Test Analysis of PHEBUS FPTO Degradation Using the ICARE2 Debris Bed Model	164
PHEBUS FPT4: Epaisseur Dissoute et Reponse Thermique Associé du Boitier	163
PHEBUS FPT4: Pre-Test Calculation for the Debris Bed Using the ICARE2V3mod0 Code (as of September 1997), JC Crestia	163
Test of DRACCAR thermo-mechanical models on a Loss of coolant accident (LOCA) in Pressurized Water Reactors (PWrs), simulation. Comparison with CATHARE2 results	160
Preliminary assessment of the DRACCAR thermo-hydraulic module. Comparison with CATHARE2 results on the simulation of a LOCA in a French PWR	160
Sviluppo e validazione di metodi e strumenti per le analisi di sicurezza: Modellistica e codici per l’analisi di incidenti severi	160
Synthesis of IPSN Pre-Test Analysis for FPT0, the First Test of the PHEBUS FP Programme	159
New ICARE 2 Calculations and Sensitivity Studies for the FPT0 Test Piloting	157
PHEBUS FPT4: Progression Axial du Bain Fondu	154
Survey on FPT-3 Objectives and Pre-Test Analyses	154
PHEBUS FPT4: Sensitivity Calculation to the Debris Bed Relocation Temperature (2573 K)	153
PHEBUS FPT4: Alternative Scenario: Steam Bypass through the Shroud	153
Investigation of Core Degradation	152
Validation and uncertainty analysis of ASTEC in early degradation phase against QUENCH-06 experiment	151
PHEBUS FPT4: Pressure Drop across the Debris Bed	151
FPT0 Bundle Calculation: ICARE2 V2 Mod1 and SCDAP/RELAP5 Mod2 Comparison	151
PHEBUS FPT4: Expected Behaviour during the Melt Progression Phase. Gas Chimney Simulation with ICARE2 V3 Mod0	148
PHEBUS FPT0 Post-test Analyses: Status of the Bundle Analysis Using ICARE/U2-MOD1 Code	147
PHEBUS FPT2: Alternative Scenario: Sudden Debris Bed Formation. ICARE2 V3 Mod0 Calculation	146
PHEBUS FPT4: Minimum Cross Section of the Steam Chimney	146
PHEBUS FPT4: Aternative Scenarios: Steam Bypass through the Shroud	146
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
ICARE2 and SCDAP/RELAP5 Result Comparison in the Post-Test Analysis of PHEBUS FPT1 Test	141
PHEBUS FPT4: Scenario Alternatif: Gonflement du Combustible	140
Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: First outcomes	137
PHEBUS FPT3: Preliminary Model for the B4C Oxidation by Steam. Exploratory Calculations using ICARE2 Code. Proposals for the Test Scenario	136
SBO analysis of a generic PWR-900 with ASTEC and MELCOR codes	92
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	80
Totale	11.044

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Categoria	#
all - tutte	43.246
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	43.246

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2020/2021	13	0	0	0	0	0	0	0	0	0	0	0	13
2021/2022	541	21	153	21	26	67	8	28	120	7	6	34	50
2022/2023	1.067	69	206	75	132	47	162	5	89	233	17	17	15
2023/2024	690	40	21	77	13	58	127	22	42	90	48	73	79
2024/2025	4.293	11	142	33	49	226	165	115	179	314	153	1.256	1.650
2025/2026	4.046	445	924	663	343	240	282	472	216	115	189	130	27
Totale													11.044