statistiche ricercatore

BANDINI, GIACOMINO

Distribuzione geografica

Continente	#
EU - Europa	7.060
NA - Nord America	6.793
AS - Asia	3.736
SA - Sud America	572
AF - Africa	126
Continente sconosciuto - Info sul continente non disponibili	31
OC - Oceania	13
Totale	18.331

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Nazione	#
US - Stati Uniti d'America	6.414
RU - Federazione Russa	4.488
SG - Singapore	1.743
CN - Cina	958
DE - Germania	643
GB - Regno Unito	571
BR - Brasile	481
SE - Svezia	462
HK - Hong Kong	363
IT - Italia	355
CA - Canada	327
FR - Francia	208
VN - Vietnam	168
JP - Giappone	143
KR - Corea	100
IN - India	92
MA - Marocco	77
FI - Finlandia	69
BE - Belgio	58
NL - Olanda	39
PL - Polonia	34
BD - Bangladesh	28
MX - Messico	27
AR - Argentina	24
IQ - Iraq	24
AT - Austria	23
ES - Italia	22
TR - Turchia	21
EC - Ecuador	17
UA - Ucraina	16
CO - Colombia	14
EU - Europa	14
TN - Tunisia	14
ID - Indonesia	13
ZA - Sudafrica	12
IE - Irlanda	11
VE - Venezuela	10
AE - Emirati Arabi Uniti	9
RO - Romania	9
UZ - Uzbekistan	9
AU - Australia	8
BO - Bolivia	8
PH - Filippine	8
PY - Paraguay	8
LT - Lituania	7
PK - Pakistan	7
TW - Taiwan	7
CH - Svizzera	6
CL - Cile	6
DZ - Algeria	6
SA - Arabia Saudita	6
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
AL - Albania	3
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
BG - Bulgaria	2
EG - Egitto	2
GE - Georgia	2
GH - Ghana	2
JO - Giordania	2
LK - Sri Lanka	2
LU - Lussemburgo	2
PA - Panama	2
PT - Portogallo	2
TT - Trinidad e Tobago	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
HT - Haiti	1
IL - Israele	1
KG - Kirghizistan	1
KH - Cambogia	1
Totale	18.307

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Città	#
Dallas	1.552
Moscow	991
Chandler	880
San Jose	802
Singapore	794
Ashburn	509
Santa Clara	315
Hamburg	311
Hefei	284
Toronto	283
San Mateo	280
Southend	280
Council Bluffs	223
Hong Kong	213
Boardman	210
Beijing	179
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	35
Washington	33
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
Frankfurt am Main	17
Nuremberg	17
Rio de Janeiro	17
Avignon	16
Central	16
London	16
Brooklyn	15
Phoenix	15
Belo Horizonte	14
Shenzhen	13
Lund	12
Rockville	12
Tong	12
Vienna	12
Atlanta	11
Denver	11
Houston	11
Manchester	11
Baghdad	10
Chicago	10
Da Nang	10
Dublin	10
Paris	10
Poplar	10
Stockholm	10
Boston	9
Dhaka	9
San Francisco	9
Genoa	8
Jakarta	8
Johannesburg	8
Mumbai	8
Borås	7
Curitiba	7
Istanbul	7
Limburg an der Lahn	7
Pisa	7
Tashkent	7
Tunis	7
Düsseldorf	6
Hillsboro	6
Mexico City	6
Portsmouth	6
Quito	6
Serra	6
St Petersburg	6
Totale	10.275

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Nome	#
Assessment of ASTEC-Na Thermal-Hydraulic Models on Experiments and Benchmarking with Other Codes	461
Analysis of ASTEC-Na capabilities for simulating a loss of flow CABRI experiment	443
Report on the Results of Analysis of DEC Events for the ETDR (ALFRED)	372
Calcoli e validazioni relativi ai codici di calcolo specifici per l’analisi degli incidenti gravi	322
Analysis of B9+ PHEBUS SFD Experiment with ICARE2 and SCDAP/RELAP 5 Codes	295
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	271
Analysis of PHEBUS FP and QUENCH Tests with ICARE2 Code and Comparison with SCDAP/RELAP5 Code Results	257
Analysis of SCARABEE BE+3 experiment with ASTEC-Na and comparison with other SFR safety analysis codes	257
ENEA activity in CESAM Project	254
ASTEC validation on TMI-2 and LOFT LP-FP-2	253
Development and Verification of Calculation Models for the Accident Analysis in Nuclear Power Plants	253
Assessment of systems codes and their coupling with CFD codes in thermal-hydraulic applications to innovative reactors	244
Analysis of Bethsy Experiment 4.3b with ASTEC VI .2 Code for CESAR Thermal-Hydraulic Module Validation	244
Analyses of an unmitigated station blackout transient with ASTEC, MAAP and MELCOR Codes	240
Assessment of the enhanced DHRS configuration for MYRRHA reactor	239
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	235
Raman/XRF/EDX microanalysis of 2nd-century stuccoes from Domus Valeriorum in Rome	235
Analysis or AEKI PWR Fuel Rod Dissolution Tests with ICARE/CATHARE andSCDAP/RELAP5 CodesAuthors: G. Bandini, S. Ederli(SAM-COLOSS-PO72 Part - A)	229
Calculation of the Phase 1 of TMI -2 Accident with ASTEC V1 Code	227
Stress-testing the ALFRED design – Part I: Impact of nuclear data uncertainties on Design Extension Conditions transients	225
Post-test of the sgtr experimental tests carried out in the LIFUS facility	221
ENEA contribution to the “Final report on system code assessment for HLM system dynamics”	220
Contributo ENEA al: 600 MWth MARS Nuclear Power Plant, Design Progress Report 1997	217
Analysis of the OECD LOFT Fission Product Experiment LP-FP-2 with ASTEC VI .2.1 Code	215
ENEA Activities in the First 6 Months of 1998	213
FP7-Maxsima work package 2 "safety analysis in support of myrrha" main outcome and conclusions	212
ENEA-PISA University Contribution to the Reinforced Concerted Action Final Report Core Degradation. Core Severe Damage Modeling	212
Bundle Calculations for PHEBUS FPT0 Test Using SCDAP/RELAP5	211
Main Specific Safety Phenomena for the LBE-Cooled XADS	209
Benchmark on Thermo-Fluid Dynamics of an Open Square Lattice Core of a Lead Cooled Reactor with SIMMER-III and FEM-LCORE Codes	209
RELAP5 assessment on CIRCE decay heat removal experiments	208
Analysis of QUENCH-O9 Test with ICARE/CATHARE Code(SAM-COLOSS-PO71 - Part B)	206
Single and two-phase sodium flow analysis for two tucop cabri tests using the ASTEC-Na code	204
Investigation of Core Degradation (COBE). Final Report	199
Transient analyses for the MYRRHA-FASTEF reactor by simmer code	199
ENEA Activities in the Last 6 Months of 1998	195
Code assessment and modelling for Design Basis Accident analysis of the European Sodium Fast Reactor design. Part II: Optimised core and representative transients analysis	192
Recent advances in ASTEC validation on circuit thermal-hydraulic and core degradation	191
Accident Control Mechanisms/Safety Limits	189
RELAP5 and SIMMER-III code assessment on CIRCE decay heat removal experiments	185
Safety studies for the MYRRHA critical core with the SIMMER-III code	184
Molten Material Relocation into the Lower Plenum: a Status Report	183
Validation of CESAR Thermal-Hydraulic Module of ASTEC V1.2 Code on BETHSY Experiments	183
First analysis of AGS0, LT2 and E9 cabri tests with the new SFR safety code ASTEC-Na	183
TMI-2 Accident Analysis with SCDAP/RELAP5 Code	181
Ex-Vessel Core Melt Stabilization Research (ECOSTAR)	179
Calculation of the PWR-1300 H3 Sequence with ASTEC V1.2 Code and Comparison with CATHARE2 V2.5 Code	179
T/H and Transient Analyses to confirm EFIT Preliminary Design	178
European activities on crosscutting thermal-hydraulic phenomena for innovative nuclear systems	177
Overview of the independent ASTEC V2.0 validation by SARNET partners	177
LBE-Water Interaction in Sub-Critical Reactors: First Experimental and Modelling Results	176
In-Vessel Core Retention Strategy (IVCRS)	175
Unlimited Cooling Capacity of the Passive-Type Emergency Core Cooling System of the Mars Reactor	175
W-DHR Testing in CIRCE Facility - RELAP5/Mod3.3 Pre.Test Calculations	173
Review of heat transfer and pressure drop correlations for liquid metal in T/H system codes	173
Code assessment and modelling for Design Basis Accident Analysis of the European sodium fast reactor design. Part I: System description, modelling and benchmarking	172
Loss of core integrity in a LFR system: models and preliminary numerical analysis	172
PHEBUS FPT-1 Benchmark: ENEA Calculations with SCDAP/RELAP5 and ICARE2 Codes	172
ICARE/CATHARE Calculation of the QUENCH-11 Experiment in the Frame of the IRSN Participation in the SARNET Benchmark	169
Interpretation of TRIGA Experimental Data with SIMMER-III Code for RELAP5 Model Evaluation and Transient Analysis	169
Post-Test Calculations for the QUENCH-01 Experiment with ICARE2 and SCDAP/RELAP5 Codes	168
Fuel dispersion and flow blockage analyses for the Myrrha-Fastef reactor by simmer code	168
Preliminary Assessment of the DIVER Concept Using Best Estimate Tools	168
JASMIN Project: Minutes of the WP2.1 Technical Meeting ENEA/Bologna, 21-22 July 2014	168
Investigation of Core Degradation (COBE)	168
Core loss during a severe accident (COLOSS)	167
Post-Test Analysis of QUENCH-11 Experiment with ICARE/CATHARE Code	167
Tridimensional analysis of local perturbations on the core reactivity and the thermal-hydraulics of the fuel elements	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	164
Use of a Multichannel Flow Model in SCDAP/RELAP5 Analysis for FPT0	162
TMI-2 Accident Analysis with ASTEC V1.1 Code and Comparison with ICARE/CATHARE and SCDAP/RELAP5	162
Ex-vessel core melt stabilization research (ECOSTAR)	161
Sviluppo e validazione di metodi e strumenti per le analisi di sicurezza: Modellistica e codici per l’analisi di incidenti severi	161
Preliminary T/H and Transient Analyses for EFIT Reactor Design	160
Ex-vessel core melt stabilization research (ECOSTAR)	159
Core Degradation and Hydrogen Generation in the TMI-2 Accident with SCDAP/RELAP5	159
Implementation and qualification of pool models in system codes	159
Evaluation of a Steam Generator Tube Rupture Accident in an Accelerator Driven System with Lead Cooling	156
Intermediate Analysis Report of PHEBUS FP Test FPT-0: Bundle Degradation and Release	156
PHEBUS FPT0: Bundle Calculations for the Reference Scenario	155
Preliminary Calculation of the Phase 2 of TMI-2 Accident with ASTEC V1 Code	155
Investigation of Core Degradation	154
FPT0 Molten Pool Analysis with SCDAP/RELAP5/MOD3.1 Code	154
FPT0 Bundle Calculation: ICARE2 V2 Mod1 and SCDAP/RELAP5 Mod2 Comparison	153
Core loss during a severe accident (COLOSS)	150
Thermal-Hydraulics of Corium Pools	144
ICARE2 and SCDAP/RELAP5 Result Comparison in the Post-Test Analysis of PHEBUS FPT1 Test	143
Pre-Test Analysis for PHEBUS FPT1 Experiment with SCADP/RELAP5/MOD3.1 Code	142
Post-Test Analysis for PHEBUS FPT0 Experiment with SCADP/RELAP5/MOD3.1 Code	142
TMI-2 Accident Analysis:2nd 8et of ICARE/CATHARE and ASTEC VI Calculations(SAM-COLOSS-P037 - Part A,B)	140
TIM-2 Accident Analysis with ASTEC V1 Code	140
Core Loss During a Severe Accident (COLOSS)	140
Interpretation of TRIGA Experimental Data with SIMMER-III Code forRELAP5 Model Evaluation and Transient Analysis	129
Totale	18.331

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Categoria	#
all - tutte	77.689
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	77.689

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2021/2022	953	0	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	6.514	744	1.409	1.078	534	364	447	850	344	232	263	198	51
2026/2027	246	85	161	0	0	0	0	0	0	0	0	0	0
Totale													18.331