statistiche ricercatore

BANDINI, GIACOMINO

Distribuzione geografica

Continente	#
EU - Europa	6.741
NA - Nord America	5.343
AS - Asia	3.261
SA - Sud America	506
AF - Africa	107
Continente sconosciuto - Info sul continente non disponibili	17
OC - Oceania	11
Totale	15.986

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Nazione	#
US - Stati Uniti d'America	4.991
RU - Federazione Russa	4.483
SG - Singapore	1.529
CN - Cina	893
DE - Germania	619
GB - Regno Unito	551
BR - Brasile	447
SE - Svezia	416
HK - Hong Kong	352
CA - Canada	315
IT - Italia	298
JP - Giappone	135
FR - Francia	100
KR - Corea	100
MA - Marocco	74
IN - India	69
FI - Finlandia	68
VN - Vietnam	57
BE - Belgio	53
NL - Olanda	29
AT - Austria	22
AR - Argentina	20
MX - Messico	20
PL - Polonia	20
IQ - Iraq	18
ES - Italia	17
BD - Bangladesh	16
TR - Turchia	16
EU - Europa	14
UA - Ucraina	13
TN - Tunisia	10
AE - Emirati Arabi Uniti	9
CO - Colombia	9
ID - Indonesia	9
UZ - Uzbekistan	8
ZA - Sudafrica	8
EC - Ecuador	7
IE - Irlanda	7
PK - Pakistan	7
RO - Romania	7
TW - Taiwan	7
AU - Australia	6
CH - Svizzera	6
LT - Lituania	6
PY - Paraguay	6
VE - Venezuela	6
BO - Bolivia	5
DO - Repubblica Dominicana	5
DZ - Algeria	5
JM - Giamaica	5
OM - Oman	5
CZ - Repubblica Ceca	4
IR - Iran	4
NP - Nepal	4
NZ - Nuova Zelanda	4
RS - Serbia	4
AZ - Azerbaigian	3
HU - Ungheria	3
KE - Kenya	3
LB - Libano	3
SA - Arabia Saudita	3
SN - Senegal	3
A1 - Anonimo	2
BG - Bulgaria	2
CL - Cile	2
CR - Costa Rica	2
GE - Georgia	2
HR - Croazia	2
JO - Giordania	2
KZ - Kazakistan	2
LK - Sri Lanka	2
LU - Lussemburgo	2
PH - Filippine	2
UY - Uruguay	2
AL - Albania	1
BA - Bosnia-Erzegovina	1
BB - Barbados	1
BY - Bielorussia	1
CI - Costa d'Avorio	1
CY - Cipro	1
DM - Dominica	1
EE - Estonia	1
EG - Egitto	1
ET - Etiopia	1
GD - Grenada	1
GR - Grecia	1
GY - Guiana	1
HN - Honduras	1
IL - Israele	1
KG - Kirghizistan	1
KH - Cambogia	1
MD - Moldavia	1
NG - Nigeria	1
NO - Norvegia	1
PA - Panama	1
PE - Perù	1
PT - Portogallo	1
SI - Slovenia	1
TV - Tuvalu	1
XK - ???statistics.table.value.countryCode.XK???	1
Totale	15.986

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Città	#
Dallas	1.547
Moscow	991
Chandler	880
Singapore	755
Hamburg	311
Ashburn	308
Santa Clara	298
Hefei	284
San Mateo	280
Southend	280
Toronto	280
Boardman	209
Hong Kong	206
Beijing	178
New York	101
Berlin	95
Seoul	95
The Dalles	75
Casablanca	69
Columbus	69
Munich	65
Los Angeles	57
Brussels	49
Helsinki	47
Redwood City	46
Falkenstein	45
Las Vegas	43
Mountain View	43
Turin	38
Council Bluffs	36
Marseille	35
Rome	34
São Paulo	34
Miami	33
Washington	32
Ann Arbor	28
Guangzhou	28
San Jose	28
Jülich	27
Bologna	22
Tokyo	21
Turku	21
Trenton	19
Amsterdam	18
Milan	18
Shanghai	18
Warsaw	18
Dong Ket	17
Montreal	17
Avignon	16
Central	16
Chennai	16
Rio de Janeiro	16
Orem	15
Brooklyn	14
Nuremberg	14
Belo Horizonte	13
Ho Chi Minh City	13
Rockville	12
Shenzhen	12
Tong	12
Vienna	11
Denver	10
Houston	10
London	10
Poplar	10
Stockholm	10
Atlanta	9
Hanoi	9
Boston	8
Dhaka	8
Genoa	8
San Francisco	8
Baghdad	7
Borås	7
Chicago	7
Curitiba	7
Frankfurt am Main	7
Jakarta	7
Paris	7
Dublin	6
Düsseldorf	6
Johannesburg	6
Manchester	6
Mumbai	6
Phoenix	6
Serra	6
Tashkent	6
Wuhan	6
Brasília	5
Lauterbourg	5
Newham	5
Portsmouth	5
St Petersburg	5
Tunis	5
Xian	5
Arona	4
Asunción	4
Campinas	4
Campo Grande	4
Totale	8.682

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Nome	#
Assessment of ASTEC-Na Thermal-Hydraulic Models on Experiments and Benchmarking with Other Codes	425
Analysis of ASTEC-Na capabilities for simulating a loss of flow CABRI experiment	419
Report on the Results of Analysis of DEC Events for the ETDR (ALFRED)	306
Calcoli e validazioni relativi ai codici di calcolo specifici per l’analisi degli incidenti gravi	293
Analysis of B9+ PHEBUS SFD Experiment with ICARE2 and SCDAP/RELAP 5 Codes	259
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	242
Analysis of PHEBUS FP and QUENCH Tests with ICARE2 Code and Comparison with SCDAP/RELAP5 Code Results	234
ASTEC validation on TMI-2 and LOFT LP-FP-2	229
Development and Verification of Calculation Models for the Accident Analysis in Nuclear Power Plants	228
Analysis of SCARABEE BE+3 experiment with ASTEC-Na and comparison with other SFR safety analysis codes	228
Analysis of Bethsy Experiment 4.3b with ASTEC VI .2 Code for CESAR Thermal-Hydraulic Module Validation	220
ENEA activity in CESAM Project	220
Analyses of an unmitigated station blackout transient with ASTEC, MAAP and MELCOR Codes	215
Assessment of systems codes and their coupling with CFD codes in thermal-hydraulic applications to innovative reactors	210
Assessment of the enhanced DHRS configuration for MYRRHA reactor	210
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	210
Analysis or AEKI PWR Fuel Rod Dissolution Tests with ICARE/CATHARE andSCDAP/RELAP5 CodesAuthors: G. Bandini, S. Ederli(SAM-COLOSS-PO72 Part - A)	204
Stress-testing the ALFRED design – Part I: Impact of nuclear data uncertainties on Design Extension Conditions transients	199
Raman/XRF/EDX microanalysis of 2nd-century stuccoes from Domus Valeriorum in Rome	199
Calculation of the Phase 1 of TMI -2 Accident with ASTEC V1 Code	195
Analysis of the OECD LOFT Fission Product Experiment LP-FP-2 with ASTEC VI .2.1 Code	195
Contributo ENEA al: 600 MWth MARS Nuclear Power Plant, Design Progress Report 1997	193
ENEA contribution to the “Final report on system code assessment for HLM system dynamics”	190
Main Specific Safety Phenomena for the LBE-Cooled XADS	189
Post-test of the sgtr experimental tests carried out in the LIFUS facility	188
ENEA-PISA University Contribution to the Reinforced Concerted Action Final Report Core Degradation. Core Severe Damage Modeling	188
Bundle Calculations for PHEBUS FPT0 Test Using SCDAP/RELAP5	186
RELAP5 assessment on CIRCE decay heat removal experiments	185
Benchmark on Thermo-Fluid Dynamics of an Open Square Lattice Core of a Lead Cooled Reactor with SIMMER-III and FEM-LCORE Codes	185
ENEA Activities in the First 6 Months of 1998	184
FP7-Maxsima work package 2 "safety analysis in support of myrrha" main outcome and conclusions	182
Analysis of QUENCH-O9 Test with ICARE/CATHARE Code(SAM-COLOSS-PO71 - Part B)	179
ENEA Activities in the Last 6 Months of 1998	175
Single and two-phase sodium flow analysis for two tucop cabri tests using the ASTEC-Na code	174
Transient analyses for the MYRRHA-FASTEF reactor by simmer code	174
Code assessment and modelling for Design Basis Accident analysis of the European Sodium Fast Reactor design. Part II: Optimised core and representative transients analysis	170
Accident Control Mechanisms/Safety Limits	165
Molten Material Relocation into the Lower Plenum: a Status Report	162
Recent advances in ASTEC validation on circuit thermal-hydraulic and core degradation	161
Investigation of Core Degradation (COBE). Final Report	160
RELAP5 and SIMMER-III code assessment on CIRCE decay heat removal experiments	157
Calculation of the PWR-1300 H3 Sequence with ASTEC V1.2 Code and Comparison with CATHARE2 V2.5 Code	156
First analysis of AGS0, LT2 and E9 cabri tests with the new SFR safety code ASTEC-Na	156
Unlimited Cooling Capacity of the Passive-Type Emergency Core Cooling System of the Mars Reactor	156
T/H and Transient Analyses to confirm EFIT Preliminary Design	154
Ex-Vessel Core Melt Stabilization Research (ECOSTAR)	154
Overview of the independent ASTEC V2.0 validation by SARNET partners	153
LBE-Water Interaction in Sub-Critical Reactors: First Experimental and Modelling Results	152
Validation of CESAR Thermal-Hydraulic Module of ASTEC V1.2 Code on BETHSY Experiments	152
Loss of core integrity in a LFR system: models and preliminary numerical analysis	152
W-DHR Testing in CIRCE Facility - RELAP5/Mod3.3 Pre.Test Calculations	151
European activities on crosscutting thermal-hydraulic phenomena for innovative nuclear systems	150
Safety studies for the MYRRHA critical core with the SIMMER-III code	150
ICARE/CATHARE Calculation of the QUENCH-11 Experiment in the Frame of the IRSN Participation in the SARNET Benchmark	149
Code assessment and modelling for Design Basis Accident Analysis of the European sodium fast reactor design. Part I: System description, modelling and benchmarking	147
Interpretation of TRIGA Experimental Data with SIMMER-III Code for RELAP5 Model Evaluation and Transient Analysis	146
Lessons Learned from the Result Comparison of Calculations of a Reference Severe Accident Sequence on a TMI-2 Like PWR Reactor of 900 MWe with the Integral Codes ASTEC and MELCOR	146
PHEBUS FPT-1 Benchmark: ENEA Calculations with SCDAP/RELAP5 and ICARE2 Codes	146
In-Vessel Core Retention Strategy (IVCRS)	145
Review of heat transfer and pressure drop correlations for liquid metal in T/H system codes	145
Investigation of Core Degradation (COBE)	145
Core loss during a severe accident (COLOSS)	144
Fuel dispersion and flow blockage analyses for the Myrrha-Fastef reactor by simmer code	144
Post-Test Analysis of QUENCH-11 Experiment with ICARE/CATHARE Code	144
JASMIN Project: Minutes of the WP2.1 Technical Meeting ENEA/Bologna, 21-22 July 2014	144
Investigation of Core Degradation	143
Use of a Multichannel Flow Model in SCDAP/RELAP5 Analysis for FPT0	143
TMI-2 Accident Analysis with ASTEC V1.1 Code and Comparison with ICARE/CATHARE and SCDAP/RELAP5	142
Sviluppo e validazione di metodi e strumenti per le analisi di sicurezza: Modellistica e codici per l’analisi di incidenti severi	142
Core Degradation and Hydrogen Generation in the TMI-2 Accident with SCDAP/RELAP5	141
Tridimensional analysis of local perturbations on the core reactivity and the thermal-hydraulics of the fuel elements	141
Evaluation of a Steam Generator Tube Rupture Accident in an Accelerator Driven System with Lead Cooling	140
Post-Test Calculations for the QUENCH-01 Experiment with ICARE2 and SCDAP/RELAP5 Codes	140
TMI-2 Accident Analysis with SCDAP/RELAP5 Code	140
Preliminary Assessment of the DIVER Concept Using Best Estimate Tools	139
Implementation and qualification of pool models in system codes	139
Ex-vessel core melt stabilization research (ECOSTAR)	137
Intermediate Analysis Report of PHEBUS FP Test FPT-0: Bundle Degradation and Release	137
Ex-vessel core melt stabilization research (ECOSTAR)	136
PHEBUS FPT0: Bundle Calculations for the Reference Scenario	136
FPT0 Molten Pool Analysis with SCDAP/RELAP5/MOD3.1 Code	135
Preliminary T/H and Transient Analyses for EFIT Reactor Design	135
FPT0 Bundle Calculation: ICARE2 V2 Mod1 and SCDAP/RELAP5 Mod2 Comparison	134
Post-Test Analysis for PHEBUS FPT0 Experiment with SCADP/RELAP5/MOD3.1 Code	128
Preliminary Calculation of the Phase 2 of TMI-2 Accident with ASTEC V1 Code	128
Pre-Test Analysis for PHEBUS FPT1 Experiment with SCADP/RELAP5/MOD3.1 Code	127
Thermal-Hydraulics of Corium Pools	126
ICARE2 and SCDAP/RELAP5 Result Comparison in the Post-Test Analysis of PHEBUS FPT1 Test	126
Core loss during a severe accident (COLOSS)	124
TIM-2 Accident Analysis with ASTEC V1 Code	123
TMI-2 Accident Analysis:2nd 8et of ICARE/CATHARE and ASTEC VI Calculations(SAM-COLOSS-P037 - Part A,B)	122
Core Loss During a Severe Accident (COLOSS)	122
Interpretation of TRIGA Experimental Data with SIMMER-III Code forRELAP5 Model Evaluation and Transient Analysis	105
Totale	15.999

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Categoria	#
all - tutte	69.322
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	69.322

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2020/2021	455	0	0	0	0	0	11	7	70	38	31	273	25
2021/2022	979	26	283	26	68	110	19	31	249	26	8	62	71
2022/2023	1.806	113	350	129	206	98	307	4	122	357	42	43	35
2023/2024	991	51	49	150	23	107	175	39	82	73	49	58	135
2024/2025	7.031	18	281	79	109	424	244	268	308	415	195	1.957	2.733
2025/2026	4.428	744	1.409	1.078	534	364	299	0	0	0	0	0	0
Totale													15.999