statistiche ricercatore

EDERLI, STEFANO

Distribuzione geografica

Continente	#
EU - Europa	4.301
NA - Nord America	3.099
AS - Asia	2.007
SA - Sud America	300
AF - Africa	59
Continente sconosciuto - Info sul continente non disponibili	11
OC - Oceania	6
Totale	9.783

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Nazione	#
US - Stati Uniti d'America	2.910
RU - Federazione Russa	2.873
SG - Singapore	941
CN - Cina	543
DE - Germania	462
GB - Regno Unito	299
BR - Brasile	264
HK - Hong Kong	249
SE - Svezia	225
IT - Italia	200
CA - Canada	162
FR - Francia	87
JP - Giappone	74
KR - Corea	63
AT - Austria	39
IN - India	39
MA - Marocco	35
FI - Finlandia	31
VN - Vietnam	31
BE - Belgio	18
MX - Messico	17
IQ - Iraq	15
PL - Polonia	15
NL - Olanda	13
AR - Argentina	12
ES - Italia	11
EU - Europa	11
TR - Turchia	10
BD - Bangladesh	9
CZ - Repubblica Ceca	9
ZA - Sudafrica	8
UZ - Uzbekistan	7
CO - Colombia	6
IR - Iran	6
AU - Australia	5
DZ - Algeria	5
EC - Ecuador	5
LT - Lituania	5
PK - Pakistan	5
TN - Tunisia	5
UA - Ucraina	4
VE - Venezuela	4
GR - Grecia	3
PY - Paraguay	3
BB - Barbados	2
CL - Cile	2
CR - Costa Rica	2
DO - Repubblica Dominicana	2
ET - Etiopia	2
HU - Ungheria	2
IL - Israele	2
KZ - Kazakistan	2
SA - Arabia Saudita	2
UY - Uruguay	2
AL - Albania	1
BH - Bahrain	1
BW - Botswana	1
CI - Costa d'Avorio	1
GA - Gabon	1
GE - Georgia	1
GT - Guatemala	1
GY - Guiana	1
HN - Honduras	1
ID - Indonesia	1
JM - Giamaica	1
JO - Giordania	1
KE - Kenya	1
LB - Libano	1
LK - Sri Lanka	1
MY - Malesia	1
NP - Nepal	1
NZ - Nuova Zelanda	1
PA - Panama	1
PE - Perù	1
PH - Filippine	1
PT - Portogallo	1
RO - Romania	1
RS - Serbia	1
SI - Slovenia	1
Totale	9.783

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Città	#
Dallas	974
Moscow	683
Chandler	506
Singapore	446
Hamburg	261
Santa Clara	178
Hefei	172
Ashburn	164
Southend	153
San Mateo	151
Toronto	151
Hong Kong	134
Boardman	129
Beijing	111
New York	101
Rome	60
Seoul	59
Berlin	52
The Dalles	47
Los Angeles	38
Casablanca	34
Munich	34
Falkenstein	26
Columbus	25
Nuremberg	25
Vienna	25
Las Vegas	24
Ann Arbor	23
Marseille	21
Washington	21
Helsinki	20
São Paulo	19
Brussels	18
Trenton	18
Bologna	17
Belo Horizonte	15
Miami	14
Mountain View	14
Paris	14
Redwood City	14
Tokyo	14
Warsaw	13
Frankfurt am Main	12
Guangzhou	12
Palermo	12
Tong	12
Ho Chi Minh City	10
Rio de Janeiro	10
Shanghai	10
Jülich	9
Turku	9
Manchester	8
Chennai	7
Council Bluffs	7
Dong Ket	7
London	7
Poplar	7
Tashkent	7
Baghdad	6
Boston	6
Curitiba	6
Gif-sur-yvette	6
Mazzano Romano	6
Milan	6
Phoenix	6
Amsterdam	5
Atlanta	5
Brno	5
Brooklyn	5
Chicago	5
Montreal	5
San Francisco	5
Wilmington	5
Borås	4
Brasília	4
Düsseldorf	4
Guayaquil	4
Hanoi	4
Houston	4
Johannesburg	4
Juiz de Fora	4
Lauterbourg	4
Mumbai	4
North Bergen	4
Orem	4
Querétaro	4
Redmond	4
Rockville	4
San Vito Lo Capo	4
Seattle	4
Serra	4
Shenzhen	4
Stockholm	4
Tehran	4
Ankara	3
Belford Roxo	3
Bochum	3
Buffalo	3
Changsha	3
Como	3
Totale	5.348

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Nome	#
Assessment of ASTEC-Na Thermal-Hydraulic Models on Experiments and Benchmarking with Other Codes	423
Analysis of ASTEC-Na capabilities for simulating a loss of flow CABRI experiment	417
Calcoli e validazioni relativi ai codici di calcolo specifici per l’analisi degli incidenti gravi	289
Analyses with MELCOR code of an unmitigated SBO scenario with in vessel retention strategy applied to a generic PWR 900 MWe	276
Analysis of B9+ PHEBUS SFD Experiment with ICARE2 and SCDAP/RELAP 5 Codes	257
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	240
Analysis of SCARABEE BE+3 experiment with ASTEC-Na and comparison with other SFR safety analysis codes	226
Development and Verification of Calculation Models for the Accident Analysis in Nuclear Power Plants	224
ENEA activity in CESAM Project	219
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	208
ASTEC code DBA analysis of a passive mitigation strategy on a generic IRIS SMR	202
DRACCAR code validation against the ballooned cluster experiment A2R038 of the ACHILLES experimental program	196
ENEA-PISA University Contribution to the Reinforced Concerted Action Final Report Core Degradation. Core Severe Damage Modeling	187
DRACCAR code validation against unballooned cluster ACHILLES experiments	187
ENEA Activities in the First 6 Months of 1998	183
Calculs complémentaires DRACCAR-2 en soutien à la préparation des essais TAGINE sur le réacteur BR2	181
Analysis of BDBA sequences in a generic IRIS reactor using ASTEC code	177
ENEA Activities in the Last 6 Months of 1998	173
Single and two-phase sodium flow analysis for two tucop cabri tests using the ASTEC-Na code	172
Synthesis of spent fuel pool accident assessments using severe accident codes	170
PHEBUS FPT3: Preliminary Investigation for Designing a Bundle with a B4C Rod	166
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	164
Exploratory ICARE 2 Calculations for the PHEBUS FPT2 Test (Bundle Aspect)	164
Investigation of Core Degradation (COBE). Final Report	158
Analysis of an unmitigated 2-inch cold leg LOCA transient with ASTEC and MELCOR codes	157
ICARE V3 Mod0 Code Validation against MP-1 Experiment	155
ICARE2 V3 Mod0 Validation against DC1 Experiment	152
PHEBUS FPT4. First Post Test Calculation on the Debris Bed Using the ICARE2 V3 Code	148
PHEBUS FPT4: Epaisseur Dissoute et Reponse Thermique Associé du Boitier	147
Synthesis of the current understanding of the PHEBUS FP FPT2 test based on the ICARE2 code calculations	147
Post Test Analysis of PHEBUS FPTO Degradation Using the ICARE2 Debris Bed Model	145
PHEBUS FPT4: Pre-Test Calculation for the Debris Bed Using the ICARE2V3mod0 Code (as of September 1997), JC Crestia	144
Investigation of Core Degradation (COBE)	144
Investigation of Core Degradation	142
PHEBUS FPT4: Progression Axial du Bain Fondu	141
Synthesis of IPSN Pre-Test Analysis for FPT0, the First Test of the PHEBUS FP Programme	141
Sviluppo e validazione di metodi e strumenti per le analisi di sicurezza: Modellistica e codici per l’analisi di incidenti severi	141
Preliminary assessment of the DRACCAR thermo-hydraulic module. Comparison with CATHARE2 results on the simulation of a LOCA in a French PWR	137
New ICARE 2 Calculations and Sensitivity Studies for the FPT0 Test Piloting	136
Survey on FPT-3 Objectives and Pre-Test Analyses	134
PHEBUS FPT4: Pressure Drop across the Debris Bed	132
FPT0 Bundle Calculation: ICARE2 V2 Mod1 and SCDAP/RELAP5 Mod2 Comparison	132
PHEBUS FPT4: Sensitivity Calculation to the Debris Bed Relocation Temperature (2573 K)	131
PHEBUS FPT4: Expected Behaviour during the Melt Progression Phase. Gas Chimney Simulation with ICARE2 V3 Mod0	131
PHEBUS FPT4: Aternative Scenarios: Steam Bypass through the Shroud	130
PHEBUS FPT4: Scenario Alternatif: Gonflement du Combustible	128
PHEBUS FPT4: Minimum Cross Section of the Steam Chimney	127
Test of DRACCAR thermo-mechanical models on a Loss of coolant accident (LOCA) in Pressurized Water Reactors (PWrs), simulation. Comparison with CATHARE2 results	125
PHEBUS FPT0 Post-test Analyses: Status of the Bundle Analysis Using ICARE/U2-MOD1 Code	124
PHEBUS FPT4: Alternative Scenario: Steam Bypass through the Shroud	124
PHEBUS FPT2: Alternative Scenario: Sudden Debris Bed Formation. ICARE2 V3 Mod0 Calculation	123
ICARE2 and SCDAP/RELAP5 Result Comparison in the Post-Test Analysis of PHEBUS FPT1 Test	123
Validation and uncertainty analysis of ASTEC in early degradation phase against QUENCH-06 experiment	119
PHEBUS FPT3: Preliminary Model for the B4C Oxidation by Steam. Exploratory Calculations using ICARE2 Code. Proposals for the Test Scenario	118
Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: First outcomes	114
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	114
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	101
null	75
SBO analysis of a generic PWR-900 with ASTEC and MELCOR codes	74
Totale	9.815

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Categoria	#
all - tutte	39.771
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	39.771

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2020/2021	259	0	0	0	0	0	8	4	42	24	19	149	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	4.359	11	142	33	49	226	165	115	180	322	161	1.277	1.678
2025/2026	2.751	455	930	671	349	245	101	0	0	0	0	0	0
Totale													9.815