statistiche ricercatore

BANDINI, GIACOMINO

Distribuzione geografica

Continente	#
NA - Nord America	7.625
EU - Europa	7.139
AS - Asia	3.790
SA - Sud America	631
AF - Africa	128
Continente sconosciuto - Info sul continente non disponibili	32
OC - Oceania	13
Totale	19.358

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Nazione	#
US - Stati Uniti d'America	7.218
RU - Federazione Russa	4.488
SG - Singapore	1.744
CN - Cina	966
DE - Germania	644
GB - Regno Unito	584
BR - Brasile	501
SE - Svezia	468
IT - Italia	395
HK - Hong Kong	364
CA - Canada	340
FR - Francia	216
VN - Vietnam	170
JP - Giappone	151
KR - Corea	101
IN - India	92
MA - Marocco	77
FI - Finlandia	69
BE - Belgio	62
NL - Olanda	39
PL - Polonia	34
BD - Bangladesh	33
EC - Ecuador	32
MX - Messico	32
CO - Colombia	30
AR - Argentina	28
IQ - Iraq	24
AT - Austria	23
ES - Italia	22
TR - Turchia	21
ID - Indonesia	20
UA - Ucraina	17
PH - Filippine	15
EU - Europa	14
TN - Tunisia	14
VE - Venezuela	13
ZA - Sudafrica	12
IE - Irlanda	11
AE - Emirati Arabi Uniti	9
RO - Romania	9
UZ - Uzbekistan	9
AU - Australia	8
BO - Bolivia	8
MY - Malesia	8
PK - Pakistan	8
PY - Paraguay	8
CL - Cile	7
JM - Giamaica	7
LT - Lituania	7
SA - Arabia Saudita	7
TW - Taiwan	7
CH - Svizzera	6
CR - Costa Rica	6
DZ - Algeria	6
NP - Nepal	6
DO - Repubblica Dominicana	5
KE - Kenya	5
OM - Oman	5
RS - Serbia	5
AL - Albania	4
AZ - Azerbaigian	4
CZ - Repubblica Ceca	4
ET - Etiopia	4
IR - Iran	4
KZ - Kazakistan	4
NZ - Nuova Zelanda	4
BG - Bulgaria	3
EE - Estonia	3
GR - Grecia	3
HR - Croazia	3
HU - Ungheria	3
LB - Libano	3
NO - Norvegia	3
PT - Portogallo	3
SK - Slovacchia (Repubblica Slovacca)	3
SN - Senegal	3
TT - Trinidad e Tobago	3
XK - ???statistics.table.value.countryCode.XK???	3
A1 - Anonimo	2
BS - Bahamas	2
EG - Egitto	2
GD - Grenada	2
GE - Georgia	2
GH - Ghana	2
JO - Giordania	2
LK - Sri Lanka	2
LU - Lussemburgo	2
MD - Moldavia	2
MQ - Martinica	2
PA - Panama	2
TH - Thailandia	2
UY - Uruguay	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
GY - Guiana	1
Totale	19.330

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Città	#
Dallas	1.554
Moscow	991
Chandler	880
San Jose	804
Singapore	795
Ashburn	701
Council Bluffs	410
Santa Clara	326
Hamburg	311
Toronto	290
Hefei	284
San Mateo	280
Southend	280
Hong Kong	213
Boardman	211
Beijing	187
New York	111
The Dalles	98
Berlin	96
Seoul	95
Lauterbourg	88
Phoenix	86
Casablanca	69
Columbus	69
Los Angeles	69
Munich	65
Ho Chi Minh City	56
Manheim	51
Brussels	49
Helsinki	48
Redwood City	46
Falkenstein	45
São Paulo	45
Las Vegas	44
Mountain View	43
Turin	42
Hanoi	41
Rome	39
Miami	37
Marseille	36
Washington	33
Orem	31
Warsaw	30
North Tonawanda	29
Ann Arbor	28
Guangzhou	28
Jülich	27
Tokyo	27
Bologna	23
Chennai	23
Milan	22
Shanghai	22
Amsterdam	21
Montreal	21
Turku	21
Trenton	19
Rio de Janeiro	18
Dong Ket	17
Frankfurt am Main	17
Nuremberg	17
Avignon	16
Brooklyn	16
Central	16
London	16
Belo Horizonte	15
Chicago	13
Shenzhen	13
Atlanta	12
Guayaquil	12
Houston	12
Lund	12
Manchester	12
Rockville	12
Tong	12
Vienna	12
Boston	11
Denver	11
North Bergen	11
Stockholm	11
Baghdad	10
Da Nang	10
Dublin	10
Paris	10
Poplar	10
San Francisco	10
Dhaka	9
Curitiba	8
Genoa	8
Jakarta	8
Johannesburg	8
Mumbai	8
Quito	8
Borås	7
Brasília	7
Cincinnati	7
Istanbul	7
Limburg an der Lahn	7
Mexico City	7
Philadelphia	7
Pisa	7
Totale	10.877

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Nome	#
Assessment of ASTEC-Na Thermal-Hydraulic Models on Experiments and Benchmarking with Other Codes	486
Analysis of ASTEC-Na capabilities for simulating a loss of flow CABRI experiment	461
Report on the Results of Analysis of DEC Events for the ETDR (ALFRED)	387
Calcoli e validazioni relativi ai codici di calcolo specifici per l’analisi degli incidenti gravi	363
Analysis of B9+ PHEBUS SFD Experiment with ICARE2 and SCDAP/RELAP 5 Codes	320
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	285
Analysis of SCARABEE BE+3 experiment with ASTEC-Na and comparison with other SFR safety analysis codes	270
Analysis of PHEBUS FP and QUENCH Tests with ICARE2 Code and Comparison with SCDAP/RELAP5 Code Results	265
ENEA activity in CESAM Project	264
ASTEC validation on TMI-2 and LOFT LP-FP-2	262
Development and Verification of Calculation Models for the Accident Analysis in Nuclear Power Plants	259
Assessment of systems codes and their coupling with CFD codes in thermal-hydraulic applications to innovative reactors	257
Analysis of Bethsy Experiment 4.3b with ASTEC VI .2 Code for CESAR Thermal-Hydraulic Module Validation	256
Assessment of the enhanced DHRS configuration for MYRRHA reactor	248
Analyses of an unmitigated station blackout transient with ASTEC, MAAP and MELCOR Codes	247
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	245
Raman/XRF/EDX microanalysis of 2nd-century stuccoes from Domus Valeriorum in Rome	244
Stress-testing the ALFRED design – Part I: Impact of nuclear data uncertainties on Design Extension Conditions transients	239
Calculation of the Phase 1 of TMI -2 Accident with ASTEC V1 Code	239
Post-test of the sgtr experimental tests carried out in the LIFUS facility	238
Analysis or AEKI PWR Fuel Rod Dissolution Tests with ICARE/CATHARE andSCDAP/RELAP5 CodesAuthors: G. Bandini, S. Ederli(SAM-COLOSS-PO72 Part - A)	236
ENEA-PISA University Contribution to the Reinforced Concerted Action Final Report Core Degradation. Core Severe Damage Modeling	235
FP7-Maxsima work package 2 "safety analysis in support of myrrha" main outcome and conclusions	232
ENEA contribution to the “Final report on system code assessment for HLM system dynamics”	227
Contributo ENEA al: 600 MWth MARS Nuclear Power Plant, Design Progress Report 1997	226
Analysis of the OECD LOFT Fission Product Experiment LP-FP-2 with ASTEC VI .2.1 Code	223
Benchmark on Thermo-Fluid Dynamics of an Open Square Lattice Core of a Lead Cooled Reactor with SIMMER-III and FEM-LCORE Codes	223
ENEA Activities in the First 6 Months of 1998	222
RELAP5 assessment on CIRCE decay heat removal experiments	221
Bundle Calculations for PHEBUS FPT0 Test Using SCDAP/RELAP5	219
Analysis of QUENCH-O9 Test with ICARE/CATHARE Code(SAM-COLOSS-PO71 - Part B)	218
Main Specific Safety Phenomena for the LBE-Cooled XADS	214
Single and two-phase sodium flow analysis for two tucop cabri tests using the ASTEC-Na code	211
First analysis of AGS0, LT2 and E9 cabri tests with the new SFR safety code ASTEC-Na	210
ENEA Activities in the Last 6 Months of 1998	209
Investigation of Core Degradation (COBE). Final Report	207
Transient analyses for the MYRRHA-FASTEF reactor by simmer code	207
Code assessment and modelling for Design Basis Accident analysis of the European Sodium Fast Reactor design. Part II: Optimised core and representative transients analysis	202
Review of heat transfer and pressure drop correlations for liquid metal in T/H system codes	201
W-DHR Testing in CIRCE Facility - RELAP5/Mod3.3 Pre.Test Calculations	200
Recent advances in ASTEC validation on circuit thermal-hydraulic and core degradation	197
RELAP5 and SIMMER-III code assessment on CIRCE decay heat removal experiments	197
Safety studies for the MYRRHA critical core with the SIMMER-III code	197
Calculation of the PWR-1300 H3 Sequence with ASTEC V1.2 Code and Comparison with CATHARE2 V2.5 Code	197
Accident Control Mechanisms/Safety Limits	197
LBE-Water Interaction in Sub-Critical Reactors: First Experimental and Modelling Results	192
Molten Material Relocation into the Lower Plenum: a Status Report	192
European activities on crosscutting thermal-hydraulic phenomena for innovative nuclear systems	189
Overview of the independent ASTEC V2.0 validation by SARNET partners	189
Validation of CESAR Thermal-Hydraulic Module of ASTEC V1.2 Code on BETHSY Experiments	188
TMI-2 Accident Analysis with SCDAP/RELAP5 Code	188
T/H and Transient Analyses to confirm EFIT Preliminary Design	187
Ex-Vessel Core Melt Stabilization Research (ECOSTAR)	186
In-Vessel Core Retention Strategy (IVCRS)	185
PHEBUS FPT-1 Benchmark: ENEA Calculations with SCDAP/RELAP5 and ICARE2 Codes	183
Loss of core integrity in a LFR system: models and preliminary numerical analysis	182
Code assessment and modelling for Design Basis Accident Analysis of the European sodium fast reactor design. Part I: System description, modelling and benchmarking	181
Post-Test Calculations for the QUENCH-01 Experiment with ICARE2 and SCDAP/RELAP5 Codes	180
Post-Test Analysis of QUENCH-11 Experiment with ICARE/CATHARE Code	180
Unlimited Cooling Capacity of the Passive-Type Emergency Core Cooling System of the Mars Reactor	179
Fuel dispersion and flow blockage analyses for the Myrrha-Fastef reactor by simmer code	178
Preliminary Assessment of the DIVER Concept Using Best Estimate Tools	178
ICARE/CATHARE Calculation of the QUENCH-11 Experiment in the Frame of the IRSN Participation in the SARNET Benchmark	178
Core loss during a severe accident (COLOSS)	177
FPT0 Bundle Calculation: ICARE2 V2 Mod1 and SCDAP/RELAP5 Mod2 Comparison	176
Interpretation of TRIGA Experimental Data with SIMMER-III Code for RELAP5 Model Evaluation and Transient Analysis	175
Investigation of Core Degradation (COBE)	174
JASMIN Project: Minutes of the WP2.1 Technical Meeting ENEA/Bologna, 21-22 July 2014	173
Tridimensional analysis of local perturbations on the core reactivity and the thermal-hydraulics of the fuel elements	170
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	170
Use of a Multichannel Flow Model in SCDAP/RELAP5 Analysis for FPT0	169
Preliminary T/H and Transient Analyses for EFIT Reactor Design	169
Ex-vessel core melt stabilization research (ECOSTAR)	168
Intermediate Analysis Report of PHEBUS FP Test FPT-0: Bundle Degradation and Release	167
Ex-vessel core melt stabilization research (ECOSTAR)	166
TMI-2 Accident Analysis with ASTEC V1.1 Code and Comparison with ICARE/CATHARE and SCDAP/RELAP5	166
Implementation and qualification of pool models in system codes	166
Evaluation of a Steam Generator Tube Rupture Accident in an Accelerator Driven System with Lead Cooling	165
Core Degradation and Hydrogen Generation in the TMI-2 Accident with SCDAP/RELAP5	165
Sviluppo e validazione di metodi e strumenti per le analisi di sicurezza: Modellistica e codici per l’analisi di incidenti severi	165
PHEBUS FPT0: Bundle Calculations for the Reference Scenario	164
Preliminary Calculation of the Phase 2 of TMI-2 Accident with ASTEC V1 Code	163
FPT0 Molten Pool Analysis with SCDAP/RELAP5/MOD3.1 Code	162
Investigation of Core Degradation	160
Core loss during a severe accident (COLOSS)	156
TMI-2 Accident Analysis:2nd 8et of ICARE/CATHARE and ASTEC VI Calculations(SAM-COLOSS-P037 - Part A,B)	156
Post-Test Analysis for PHEBUS FPT0 Experiment with SCADP/RELAP5/MOD3.1 Code	153
Thermal-Hydraulics of Corium Pools	153
Pre-Test Analysis for PHEBUS FPT1 Experiment with SCADP/RELAP5/MOD3.1 Code	151
ICARE2 and SCDAP/RELAP5 Result Comparison in the Post-Test Analysis of PHEBUS FPT1 Test	150
Core Loss During a Severe Accident (COLOSS)	147
TIM-2 Accident Analysis with ASTEC V1 Code	146
Interpretation of TRIGA Experimental Data with SIMMER-III Code forRELAP5 Model Evaluation and Transient Analysis	138
Totale	19.358

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Categoria	#
all - tutte	80.843
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	80.843

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2021/2022	644	0	0	0	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	1.273	85	264	473	451	0	0	0	0	0	0	0	0
Totale													19.358