statistiche ricercatore

BANDINI, GIACOMINO

Distribuzione geografica

Continente	#
EU - Europa	6.729
NA - Nord America	5.235
AS - Asia	3.215
SA - Sud America	503
AF - Africa	107
Continente sconosciuto - Info sul continente non disponibili	17
OC - Oceania	11
Totale	15.817

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Nazione	#
US - Stati Uniti d'America	4.888
RU - Federazione Russa	4.483
SG - Singapore	1.496
CN - Cina	893
DE - Germania	619
GB - Regno Unito	547
BR - Brasile	444
SE - Svezia	413
HK - Hong Kong	352
CA - Canada	311
IT - Italia	297
JP - Giappone	131
FR - Francia	100
KR - Corea	100
MA - Marocco	74
FI - Finlandia	68
IN - India	64
VN - Vietnam	57
BE - Belgio	53
NL - Olanda	29
AT - Austria	22
AR - Argentina	20
MX - Messico	19
PL - Polonia	19
IQ - Iraq	18
TR - Turchia	15
BD - Bangladesh	14
ES - Italia	14
EU - Europa	14
UA - Ucraina	13
TN - Tunisia	10
CO - Colombia	9
ID - Indonesia	9
AE - Emirati Arabi Uniti	8
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	15.817

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Città	#
Dallas	1.547
Moscow	991
Chandler	880
Singapore	735
Hamburg	311
Santa Clara	298
Hefei	284
San Mateo	280
Southend	280
Toronto	279
Ashburn	276
Boardman	209
Hong Kong	206
Beijing	178
Berlin	95
Seoul	95
New York	93
The Dalles	75
Casablanca	69
Columbus	69
Munich	65
Los Angeles	51
Brussels	49
Helsinki	47
Redwood City	46
Falkenstein	45
Las Vegas	43
Mountain View	43
Turin	38
Council Bluffs	36
Marseille	35
Miami	33
Rome	33
São Paulo	32
Washington	32
Ann Arbor	28
Guangzhou	28
Jülich	27
Bologna	22
Turku	21
Trenton	19
Amsterdam	18
Milan	18
Shanghai	18
Dong Ket	17
Tokyo	17
Warsaw	17
Avignon	16
Central	16
Rio de Janeiro	16
Montreal	14
Nuremberg	14
Belo Horizonte	13
Brooklyn	13
Chennai	13
Ho Chi Minh City	13
Rockville	12
Shenzhen	12
Tong	12
Vienna	11
London	10
Hanoi	9
Houston	9
Denver	8
Genoa	8
Orem	8
San Francisco	8
Atlanta	7
Baghdad	7
Borås	7
Boston	7
Chicago	7
Curitiba	7
Dhaka	7
Frankfurt am Main	7
Jakarta	7
Paris	7
Poplar	7
Stockholm	7
Dublin	6
Düsseldorf	6
Johannesburg	6
Phoenix	6
Serra	6
Tashkent	6
Wuhan	6
Brasília	5
Lauterbourg	5
Manchester	5
Newham	5
Portsmouth	5
San Jose	5
St Petersburg	5
Tunis	5
Xian	5
Arona	4
Asunción	4
Campinas	4
Campo Grande	4
Cincinnati	4
Totale	8.554

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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
Report on the Results of Analysis of DEC Events for the ETDR (ALFRED)	305
Calcoli e validazioni relativi ai codici di calcolo specifici per l’analisi degli incidenti gravi	289
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 PHEBUS FP and QUENCH Tests with ICARE2 Code and Comparison with SCDAP/RELAP5 Code Results	232
ASTEC validation on TMI-2 and LOFT LP-FP-2	227
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
Analysis of Bethsy Experiment 4.3b with ASTEC VI .2 Code for CESAR Thermal-Hydraulic Module Validation	219
ENEA activity in CESAM Project	219
Analyses of an unmitigated station blackout transient with ASTEC, MAAP and MELCOR Codes	213
Assessment of the enhanced DHRS configuration for MYRRHA reactor	208
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
Assessment of systems codes and their coupling with CFD codes in thermal-hydraulic applications to innovative reactors	207
Analysis or AEKI PWR Fuel Rod Dissolution Tests with ICARE/CATHARE andSCDAP/RELAP5 CodesAuthors: G. Bandini, S. Ederli(SAM-COLOSS-PO72 Part - A)	201
Stress-testing the ALFRED design – Part I: Impact of nuclear data uncertainties on Design Extension Conditions transients	198
Raman/XRF/EDX microanalysis of 2nd-century stuccoes from Domus Valeriorum in Rome	198
Calculation of the Phase 1 of TMI -2 Accident with ASTEC V1 Code	194
Analysis of the OECD LOFT Fission Product Experiment LP-FP-2 with ASTEC VI .2.1 Code	193
Contributo ENEA al: 600 MWth MARS Nuclear Power Plant, Design Progress Report 1997	192
ENEA contribution to the “Final report on system code assessment for HLM system dynamics”	189
Post-test of the sgtr experimental tests carried out in the LIFUS facility	187
ENEA-PISA University Contribution to the Reinforced Concerted Action Final Report Core Degradation. Core Severe Damage Modeling	187
Main Specific Safety Phenomena for the LBE-Cooled XADS	187
Bundle Calculations for PHEBUS FPT0 Test Using SCDAP/RELAP5	185
RELAP5 assessment on CIRCE decay heat removal experiments	184
Benchmark on Thermo-Fluid Dynamics of an Open Square Lattice Core of a Lead Cooled Reactor with SIMMER-III and FEM-LCORE Codes	184
ENEA Activities in the First 6 Months of 1998	182
FP7-Maxsima work package 2 "safety analysis in support of myrrha" main outcome and conclusions	178
Analysis of QUENCH-O9 Test with ICARE/CATHARE Code(SAM-COLOSS-PO71 - Part B)	178
ENEA Activities in the Last 6 Months of 1998	173
Transient analyses for the MYRRHA-FASTEF reactor by simmer code	173
Single and two-phase sodium flow analysis for two tucop cabri tests using the ASTEC-Na code	172
Code assessment and modelling for Design Basis Accident analysis of the European Sodium Fast Reactor design. Part II: Optimised core and representative transients analysis	169
Accident Control Mechanisms/Safety Limits	164
Molten Material Relocation into the Lower Plenum: a Status Report	159
Recent advances in ASTEC validation on circuit thermal-hydraulic and core degradation	158
Investigation of Core Degradation (COBE). Final Report	158
Calculation of the PWR-1300 H3 Sequence with ASTEC V1.2 Code and Comparison with CATHARE2 V2.5 Code	155
Unlimited Cooling Capacity of the Passive-Type Emergency Core Cooling System of the Mars Reactor	154
RELAP5 and SIMMER-III code assessment on CIRCE decay heat removal experiments	153
First analysis of AGS0, LT2 and E9 cabri tests with the new SFR safety code ASTEC-Na	153
T/H and Transient Analyses to confirm EFIT Preliminary Design	152
Ex-Vessel Core Melt Stabilization Research (ECOSTAR)	152
LBE-Water Interaction in Sub-Critical Reactors: First Experimental and Modelling Results	151
Overview of the independent ASTEC V2.0 validation by SARNET partners	151
Loss of core integrity in a LFR system: models and preliminary numerical analysis	150
Safety studies for the MYRRHA critical core with the SIMMER-III code	149
Validation of CESAR Thermal-Hydraulic Module of ASTEC V1.2 Code on BETHSY Experiments	149
W-DHR Testing in CIRCE Facility - RELAP5/Mod3.3 Pre.Test Calculations	149
European activities on crosscutting thermal-hydraulic phenomena for innovative nuclear systems	148
ICARE/CATHARE Calculation of the QUENCH-11 Experiment in the Frame of the IRSN Participation in the SARNET Benchmark	146
Code assessment and modelling for Design Basis Accident Analysis of the European sodium fast reactor design. Part I: System description, modelling and benchmarking	145
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	145
Review of heat transfer and pressure drop correlations for liquid metal in T/H system codes	144
Investigation of Core Degradation (COBE)	144
Fuel dispersion and flow blockage analyses for the Myrrha-Fastef reactor by simmer code	143
In-Vessel Core Retention Strategy (IVCRS)	143
Interpretation of TRIGA Experimental Data with SIMMER-III Code for RELAP5 Model Evaluation and Transient Analysis	143
Core loss during a severe accident (COLOSS)	142
Investigation of Core Degradation	142
Use of a Multichannel Flow Model in SCDAP/RELAP5 Analysis for FPT0	142
JASMIN Project: Minutes of the WP2.1 Technical Meeting ENEA/Bologna, 21-22 July 2014	142
TMI-2 Accident Analysis with ASTEC V1.1 Code and Comparison with ICARE/CATHARE and SCDAP/RELAP5	141
Sviluppo e validazione di metodi e strumenti per le analisi di sicurezza: Modellistica e codici per l’analisi di incidenti severi	141
PHEBUS FPT-1 Benchmark: ENEA Calculations with SCDAP/RELAP5 and ICARE2 Codes	141
Post-Test Analysis of QUENCH-11 Experiment with ICARE/CATHARE Code	140
Tridimensional analysis of local perturbations on the core reactivity and the thermal-hydraulics of the fuel elements	140
Core Degradation and Hydrogen Generation in the TMI-2 Accident with SCDAP/RELAP5	139
Post-Test Calculations for the QUENCH-01 Experiment with ICARE2 and SCDAP/RELAP5 Codes	139
Evaluation of a Steam Generator Tube Rupture Accident in an Accelerator Driven System with Lead Cooling	138
Implementation and qualification of pool models in system codes	138
Preliminary Assessment of the DIVER Concept Using Best Estimate Tools	137
TMI-2 Accident Analysis with SCDAP/RELAP5 Code	137
Ex-vessel core melt stabilization research (ECOSTAR)	136
Ex-vessel core melt stabilization research (ECOSTAR)	135
Intermediate Analysis Report of PHEBUS FP Test FPT-0: Bundle Degradation and Release	135
PHEBUS FPT0: Bundle Calculations for the Reference Scenario	135
FPT0 Molten Pool Analysis with SCDAP/RELAP5/MOD3.1 Code	133
Preliminary T/H and Transient Analyses for EFIT Reactor Design	133
FPT0 Bundle Calculation: ICARE2 V2 Mod1 and SCDAP/RELAP5 Mod2 Comparison	132
Post-Test Analysis for PHEBUS FPT0 Experiment with SCADP/RELAP5/MOD3.1 Code	127
Preliminary Calculation of the Phase 2 of TMI-2 Accident with ASTEC V1 Code	127
Pre-Test Analysis for PHEBUS FPT1 Experiment with SCADP/RELAP5/MOD3.1 Code	126
Thermal-Hydraulics of Corium Pools	124
Core loss during a severe accident (COLOSS)	123
ICARE2 and SCDAP/RELAP5 Result Comparison in the Post-Test Analysis of PHEBUS FPT1 Test	123
TMI-2 Accident Analysis:2nd 8et of ICARE/CATHARE and ASTEC VI Calculations(SAM-COLOSS-P037 - Part A,B)	121
TIM-2 Accident Analysis with ASTEC V1 Code	121
Core Loss During a Severe Accident (COLOSS)	121
Interpretation of TRIGA Experimental Data with SIMMER-III Code forRELAP5 Model Evaluation and Transient Analysis	103
Totale	15.830

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Categoria	#
all - tutte	68.926
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	68.926

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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	4.259	744	1.409	1.078	534	364	130	0	0	0	0	0	0
Totale													15.830