statistiche ricercatore

BANDINI, GIACOMINO

Distribuzione geografica

Continente	#
EU - Europa	6.985
NA - Nord America	6.623
AS - Asia	3.726
SA - Sud America	564
AF - Africa	126
Continente sconosciuto - Info sul continente non disponibili	18
OC - Oceania	13
Totale	18.055

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Nazione	#
US - Stati Uniti d'America	6.253
RU - Federazione Russa	4.488
SG - Singapore	1.741
CN - Cina	954
DE - Germania	639
GB - Regno Unito	571
BR - Brasile	477
SE - Svezia	433
HK - Hong Kong	362
IT - Italia	328
CA - Canada	325
FR - Francia	202
VN - Vietnam	168
JP - Giappone	143
KR - Corea	100
IN - India	92
MA - Marocco	77
FI - Finlandia	69
BE - Belgio	58
NL - Olanda	37
PL - Polonia	32
BD - Bangladesh	26
MX - Messico	25
AR - Argentina	24
IQ - Iraq	24
AT - Austria	23
ES - Italia	21
TR - Turchia	21
EC - Ecuador	16
UA - Ucraina	16
EU - Europa	14
TN - Tunisia	14
CO - Colombia	13
ID - Indonesia	13
ZA - Sudafrica	12
IE - Irlanda	11
VE - Venezuela	10
AE - Emirati Arabi Uniti	9
UZ - Uzbekistan	9
AU - Australia	8
BO - Bolivia	8
PH - Filippine	8
RO - Romania	8
PK - Pakistan	7
PY - Paraguay	7
TW - Taiwan	7
CH - Svizzera	6
DZ - Algeria	6
LT - Lituania	6
SA - Arabia Saudita	6
CL - Cile	5
DO - Repubblica Dominicana	5
JM - Giamaica	5
NP - Nepal	5
OM - Oman	5
RS - Serbia	5
AZ - Azerbaigian	4
CR - Costa Rica	4
CZ - Repubblica Ceca	4
IR - Iran	4
KE - Kenya	4
NZ - Nuova Zelanda	4
ET - Etiopia	3
GR - Grecia	3
HR - Croazia	3
HU - Ungheria	3
KZ - Kazakistan	3
LB - Libano	3
NO - Norvegia	3
SK - Slovacchia (Repubblica Slovacca)	3
SN - Senegal	3
A1 - Anonimo	2
AL - Albania	2
BG - Bulgaria	2
EG - Egitto	2
GE - Georgia	2
GH - Ghana	2
JO - Giordania	2
LK - Sri Lanka	2
LU - Lussemburgo	2
UY - Uruguay	2
XK - ???statistics.table.value.countryCode.XK???	2
AO - Angola	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
GD - Grenada	1
GY - Guiana	1
HN - Honduras	1
IL - Israele	1
KG - Kirghizistan	1
KH - Cambogia	1
MD - Moldavia	1
MK - Macedonia	1
MN - Mongolia	1
MQ - Martinica	1
Totale	18.048

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Città	#
Dallas	1.552
Moscow	991
Chandler	880
Singapore	793
San Jose	789
Ashburn	502
Hamburg	311
Santa Clara	310
Hefei	284
Toronto	282
San Mateo	280
Southend	280
Hong Kong	212
Boardman	209
Beijing	178
Council Bluffs	128
New York	111
The Dalles	98
Berlin	95
Seoul	95
Lauterbourg	88
Casablanca	69
Columbus	69
Los Angeles	66
Munich	65
Ho Chi Minh City	56
Brussels	49
Helsinki	48
Redwood City	46
Falkenstein	45
Las Vegas	43
Mountain View	43
Turin	41
Hanoi	40
São Paulo	40
Marseille	36
Rome	36
Miami	34
Washington	32
Orem	31
Warsaw	30
Ann Arbor	28
Guangzhou	28
Jülich	27
Tokyo	25
Chennai	23
Bologna	22
Shanghai	22
Amsterdam	21
Montreal	21
Turku	21
Milan	19
Trenton	19
Dong Ket	17
Nuremberg	17
Rio de Janeiro	17
Avignon	16
Central	16
London	16
Brooklyn	15
Belo Horizonte	14
Frankfurt am Main	13
Shenzhen	13
Lund	12
Rockville	12
Tong	12
Vienna	12
Atlanta	11
Manchester	11
Baghdad	10
Da Nang	10
Denver	10
Dublin	10
Houston	10
Paris	10
Poplar	10
Stockholm	10
Boston	9
Dhaka	9
San Francisco	9
Chicago	8
Genoa	8
Jakarta	8
Johannesburg	8
Mumbai	8
Phoenix	8
Borås	7
Curitiba	7
Istanbul	7
Limburg an der Lahn	7
Tashkent	7
Tunis	7
Düsseldorf	6
Hillsboro	6
Mexico City	6
Portsmouth	6
Serra	6
St Petersburg	6
Wuhan	6
Brasília	5
Totale	10.131

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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
Report on the Results of Analysis of DEC Events for the ETDR (ALFRED)	353
Calcoli e validazioni relativi ai codici di calcolo specifici per l’analisi degli incidenti gravi	319
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 PHEBUS FP and QUENCH Tests with ICARE2 Code and Comparison with SCDAP/RELAP5 Code Results	255
Analysis of SCARABEE BE+3 experiment with ASTEC-Na and comparison with other SFR safety analysis codes	254
ASTEC validation on TMI-2 and LOFT LP-FP-2	250
ENEA activity in CESAM Project	250
Development and Verification of Calculation Models for the Accident Analysis in Nuclear Power Plants	250
Analysis of Bethsy Experiment 4.3b with ASTEC VI .2 Code for CESAR Thermal-Hydraulic Module Validation	242
Assessment of systems codes and their coupling with CFD codes in thermal-hydraulic applications to innovative reactors	240
Analyses of an unmitigated station blackout transient with ASTEC, MAAP and MELCOR Codes	238
Assessment of the enhanced DHRS configuration for MYRRHA reactor	236
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
Raman/XRF/EDX microanalysis of 2nd-century stuccoes from Domus Valeriorum in Rome	232
Analysis or AEKI PWR Fuel Rod Dissolution Tests with ICARE/CATHARE andSCDAP/RELAP5 CodesAuthors: G. Bandini, S. Ederli(SAM-COLOSS-PO72 Part - A)	227
Calculation of the Phase 1 of TMI -2 Accident with ASTEC V1 Code	225
Stress-testing the ALFRED design – Part I: Impact of nuclear data uncertainties on Design Extension Conditions transients	221
Post-test of the sgtr experimental tests carried out in the LIFUS facility	217
ENEA contribution to the “Final report on system code assessment for HLM system dynamics”	217
Analysis of the OECD LOFT Fission Product Experiment LP-FP-2 with ASTEC VI .2.1 Code	213
Contributo ENEA al: 600 MWth MARS Nuclear Power Plant, Design Progress Report 1997	212
FP7-Maxsima work package 2 "safety analysis in support of myrrha" main outcome and conclusions	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
Bundle Calculations for PHEBUS FPT0 Test Using SCDAP/RELAP5	209
Main Specific Safety Phenomena for the LBE-Cooled XADS	207
Benchmark on Thermo-Fluid Dynamics of an Open Square Lattice Core of a Lead Cooled Reactor with SIMMER-III and FEM-LCORE Codes	206
RELAP5 assessment on CIRCE decay heat removal experiments	205
Analysis of QUENCH-O9 Test with ICARE/CATHARE Code(SAM-COLOSS-PO71 - Part B)	204
Single and two-phase sodium flow analysis for two tucop cabri tests using the ASTEC-Na code	201
Transient analyses for the MYRRHA-FASTEF reactor by simmer code	198
Investigation of Core Degradation (COBE). Final Report	196
ENEA Activities in the Last 6 Months of 1998	193
Code assessment and modelling for Design Basis Accident analysis of the European Sodium Fast Reactor design. Part II: Optimised core and representative transients analysis	190
Recent advances in ASTEC validation on circuit thermal-hydraulic and core degradation	187
Accident Control Mechanisms/Safety Limits	187
RELAP5 and SIMMER-III code assessment on CIRCE decay heat removal experiments	180
Molten Material Relocation into the Lower Plenum: a Status Report	180
First analysis of AGS0, LT2 and E9 cabri tests with the new SFR safety code ASTEC-Na	180
Calculation of the PWR-1300 H3 Sequence with ASTEC V1.2 Code and Comparison with CATHARE2 V2.5 Code	178
Validation of CESAR Thermal-Hydraulic Module of ASTEC V1.2 Code on BETHSY Experiments	177
European activities on crosscutting thermal-hydraulic phenomena for innovative nuclear systems	176
Overview of the independent ASTEC V2.0 validation by SARNET partners	176
Ex-Vessel Core Melt Stabilization Research (ECOSTAR)	176
T/H and Transient Analyses to confirm EFIT Preliminary Design	175
Safety studies for the MYRRHA critical core with the SIMMER-III code	175
LBE-Water Interaction in Sub-Critical Reactors: First Experimental and Modelling Results	174
TMI-2 Accident Analysis with SCDAP/RELAP5 Code	174
Unlimited Cooling Capacity of the Passive-Type Emergency Core Cooling System of the Mars Reactor	173
Code assessment and modelling for Design Basis Accident Analysis of the European sodium fast reactor design. Part I: System description, modelling and benchmarking	171
W-DHR Testing in CIRCE Facility - RELAP5/Mod3.3 Pre.Test Calculations	171
Loss of core integrity in a LFR system: models and preliminary numerical analysis	171
Review of heat transfer and pressure drop correlations for liquid metal in T/H system codes	170
In-Vessel Core Retention Strategy (IVCRS)	169
PHEBUS FPT-1 Benchmark: ENEA Calculations with SCDAP/RELAP5 and ICARE2 Codes	169
ICARE/CATHARE Calculation of the QUENCH-11 Experiment in the Frame of the IRSN Participation in the SARNET Benchmark	168
Investigation of Core Degradation (COBE)	167
Fuel dispersion and flow blockage analyses for the Myrrha-Fastef reactor by simmer code	166
JASMIN Project: Minutes of the WP2.1 Technical Meeting ENEA/Bologna, 21-22 July 2014	166
Post-Test Calculations for the QUENCH-01 Experiment with ICARE2 and SCDAP/RELAP5 Codes	165
Post-Test Analysis of QUENCH-11 Experiment with ICARE/CATHARE Code	165
Core loss during a severe accident (COLOSS)	164
Preliminary Assessment of the DIVER Concept Using Best Estimate Tools	164
Interpretation of TRIGA Experimental Data with SIMMER-III Code for RELAP5 Model Evaluation and Transient Analysis	164
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	163
Use of a Multichannel Flow Model in SCDAP/RELAP5 Analysis for FPT0	161
Tridimensional analysis of local perturbations on the core reactivity and the thermal-hydraulics of the fuel elements	161
TMI-2 Accident Analysis with ASTEC V1.1 Code and Comparison with ICARE/CATHARE and SCDAP/RELAP5	160
Sviluppo e validazione di metodi e strumenti per le analisi di sicurezza: Modellistica e codici per l’analisi di incidenti severi	160
Ex-vessel core melt stabilization research (ECOSTAR)	159
Core Degradation and Hydrogen Generation in the TMI-2 Accident with SCDAP/RELAP5	158
Implementation and qualification of pool models in system codes	157
Ex-vessel core melt stabilization research (ECOSTAR)	156
Preliminary T/H and Transient Analyses for EFIT Reactor Design	156
Intermediate Analysis Report of PHEBUS FP Test FPT-0: Bundle Degradation and Release	154
Evaluation of a Steam Generator Tube Rupture Accident in an Accelerator Driven System with Lead Cooling	153
FPT0 Molten Pool Analysis with SCDAP/RELAP5/MOD3.1 Code	153
PHEBUS FPT0: Bundle Calculations for the Reference Scenario	153
Investigation of Core Degradation	152
Preliminary Calculation of the Phase 2 of TMI-2 Accident with ASTEC V1 Code	152
FPT0 Bundle Calculation: ICARE2 V2 Mod1 and SCDAP/RELAP5 Mod2 Comparison	151
Core loss during a severe accident (COLOSS)	148
Thermal-Hydraulics of Corium Pools	143
ICARE2 and SCDAP/RELAP5 Result Comparison in the Post-Test Analysis of PHEBUS FPT1 Test	142
Post-Test Analysis for PHEBUS FPT0 Experiment with SCADP/RELAP5/MOD3.1 Code	141
Pre-Test Analysis for PHEBUS FPT1 Experiment with SCADP/RELAP5/MOD3.1 Code	140
TMI-2 Accident Analysis:2nd 8et of ICARE/CATHARE and ASTEC VI Calculations(SAM-COLOSS-P037 - Part A,B)	139
TIM-2 Accident Analysis with ASTEC V1 Code	138
Core Loss During a Severe Accident (COLOSS)	138
Interpretation of TRIGA Experimental Data with SIMMER-III Code forRELAP5 Model Evaluation and Transient Analysis	124
Totale	18.068

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Categoria	#
all - tutte	75.516
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	75.516

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2020/2021	25	0	0	0	0	0	0	0	0	0	0	0	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	6.497	744	1.409	1.078	534	364	447	850	344	232	263	198	34
Totale													18.068