RE.PUBLIC@POLIMI pubblicazioni di ricerca del Politecnico di Milano

GIACOBBO, FRANCESCA CELSA
 Distribuzione geografica
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Continente #
NA - Nord America 5.309
EU - Europa 3.187
AS - Asia 2.241
SA - Sud America 465
AF - Africa 129
OC - Oceania 8
Continente sconosciuto - Info sul continente non disponibili 6
Totale 11.345
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Nazione #
US - Stati Uniti d'America 5.194
RU - Federazione Russa 1.203
SG - Singapore 673
CN - Cina 625
IT - Italia 573
BR - Brasile 387
VN - Vietnam 291
AT - Austria 283
KR - Corea 154
DE - Germania 150
GB - Regno Unito 145
FR - Francia 141
FI - Finlandia 132
JP - Giappone 130
SE - Svezia 118
NL - Olanda 112
UA - Ucraina 107
CA - Canada 77
IE - Irlanda 62
HK - Hong Kong 54
IN - India 48
ES - Italia 47
JO - Giordania 42
MA - Marocco 41
ID - Indonesia 40
ZA - Sudafrica 31
AR - Argentina 29
BE - Belgio 28
TR - Turchia 27
MX - Messico 23
BD - Bangladesh 21
IQ - Iraq 20
TW - Taiwan 18
EG - Egitto 17
PL - Polonia 16
CH - Svizzera 14
BG - Bulgaria 13
CO - Colombia 13
DZ - Algeria 12
IR - Iran 12
EC - Ecuador 11
CL - Cile 10
PK - Pakistan 10
RS - Serbia 8
SA - Arabia Saudita 8
LT - Lituania 7
AE - Emirati Arabi Uniti 6
AU - Australia 6
CI - Costa d'Avorio 6
ET - Etiopia 6
IL - Israele 6
PH - Filippine 6
PY - Paraguay 6
EU - Europa 5
MY - Malesia 5
TH - Thailandia 5
UZ - Uzbekistan 5
AZ - Azerbaigian 4
BA - Bosnia-Erzegovina 4
CZ - Repubblica Ceca 4
NP - Nepal 4
PE - Perù 4
TT - Trinidad e Tobago 4
GE - Georgia 3
HN - Honduras 3
HU - Ungheria 3
KG - Kirghizistan 3
OM - Oman 3
SN - Senegal 3
TN - Tunisia 3
UY - Uruguay 3
AM - Armenia 2
AO - Angola 2
BH - Bahrain 2
BJ - Benin 2
DK - Danimarca 2
GR - Grecia 2
HR - Croazia 2
JM - Giamaica 2
KE - Kenya 2
KZ - Kazakistan 2
MD - Moldavia 2
NZ - Nuova Zelanda 2
PA - Panama 2
PS - Palestinian Territory 2
PT - Portogallo 2
QA - Qatar 2
RO - Romania 2
SI - Slovenia 2
SY - Repubblica araba siriana 2
VE - Venezuela 2
AI - Anguilla 1
CR - Costa Rica 1
CY - Cipro 1
EE - Estonia 1
GD - Grenada 1
KH - Cambogia 1
KW - Kuwait 1
LI - Liechtenstein 1
LK - Sri Lanka 1
Totale 11.336
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Città #
Ashburn 671
San Jose 411
Santa Clara 390
Singapore 376
Woodbridge 349
Fairfield 338
Chandler 308
Vienna 273
Ann Arbor 225
Wilmington 179
Moscow 172
Milan 170
Houston 161
Seattle 146
Hefei 142
The Dalles 132
Council Bluffs 126
Seoul 124
Cambridge 108
Tokyo 104
Beijing 85
Jacksonville 80
Boardman 79
Los Angeles 74
Dallas 73
Ho Chi Minh City 73
Lauterbourg 72
Dearborn 66
Lawrence 66
Helsinki 65
Hanoi 59
Dublin 58
Kent 57
Medford 57
New York 47
Hong Kong 44
London 42
Ottawa 41
Amman 40
Dong Ket 37
São Paulo 37
Amsterdam 33
Auburn Hills 31
Buffalo 30
Frankfurt am Main 29
North Charleston 29
Des Moines 28
San Diego 28
Las Vegas 27
Orem 26
Málaga 25
Rome 25
Casablanca 24
Shanghai 22
Brussels 19
Zhengzhou 17
Atlanta 16
Chicago 16
Jakarta 16
Johannesburg 16
Montreal 16
Redmond 16
Reno 16
Munich 14
Stockholm 14
Princeton 13
Rio de Janeiro 13
Taipei 13
Da Nang 12
Guangzhou 12
Kenitra 12
Sofia 12
Washington 12
Baghdad 11
San Francisco 11
Warsaw 11
Brooklyn 10
Curitiba 9
Hillsboro 9
Madrid 9
Nuremberg 9
Paris 9
Reghaïa 9
Turin 9
Dhaka 8
Haiphong 8
Hangzhou 8
Istanbul 8
Manchester 8
Norwalk 8
Provo 8
Redwood City 8
Roubaix 8
Shijiazhuang 8
Turku 8
Ankara 7
Belo Horizonte 7
Campinas 7
Columbus 7
Delft 7
Totale 7.018
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Nome #
Pyroprocess Experiments at ENEA Laboratories 336
Effect of Gamma Irradiation on Poly(Butylene Naphthalate) Based Polyesters 312
A case study of management and disposal of tenorms: Radiological risk estimation by tsd dose and resrad-onsite 281
Development of an OpenFOAM multiphysics solver for solid fission products transport in the Molten Salt Fast Reactor 242
Adsorption of uranium, cesium and strontium onto coconut shell activated carbon 238
An experimental study on Sodalite and SAP matrices for immobilization of spent chloride salt waste 238
A study on sodalite pellets as matrix for spent chloride salts confinement 230
Application of the dynamic mode decomposition approach to the dispersion of radioactive contaminants in air 222
Leaching behavior of salt wastes conditioned with sodalite blended with two different glass powders 215
A Serpent/OpenFOAM coupling approach for the study of the fuel burnup 200
Competitive Sorption of Metal Ions from Aqueous Solution onto Sand 197
Study of the absorption spectra of Fricke xylenol orange gel dosimeters 194
Conditioning of chloride salt wastes from pyroprocesses through the pressureless consolidation process 191
A nuclear measurement technique of water penetration in concrete barriers 189
A Nuclear Measurement Technique of Water Penetration in Concrete Barriers 187
Advanced Modelling And Stability Analysis For Nuclear Reactors 184
A Kalman Filter-Based Approach for Online Source-Term Estimation in Accidental Radioactive Dispersion Events 182
Study on Characteristics of Fricke Xylenol Orange Gelatin Dosimeters( 179
Dynamic mode decomposition for the stability analysis of the Molten Salt Fast Reactor core 179
Effects of the pre-irradiation storage procedure on the dose response of a Fricke xylenol orange gel dosimeter 179
Adsorption and competitive adsorption of metal ions from aqueous solution onto sand and silica colloids. 171
An Eulerian Single-Phase Transport Model for Solid Fission Products in the Molten Salt Fast Reactor: Development of an Analytical Solution for Verification Purposes 171
Competitive Sorption of Metal Ions from Aqueous Solution onto Sand 170
About the dependence of breakthrough curves on flow direction in column experiments of transport across a sharp interface separating different porous materials 164
An Alternative Approach for Group Constants Regression Based on Supervised Learning Techniques 163
Countering radiological and nuclear threats. Proceedings of the 4th International CBRNe Workshop, "IW CBRNe 2018" 163
Modeling the effects of the engineered barriers of a radioactive waste repository by Monte Carlo simulation 158
A Feasibility Study on In-Core Fuel Management via Quantum Particle Swarm Optimization 155
Multiphysics analysis of RANS-based turbulent transport of solid fission products in the Molten Salt Fast Reactor 155
Competitive sorption of Cs+, Sr+, Cu2+ ions from aqueous solution onto silica sand 153
Effect of pH on cation release from sodalite -based matrices for immobilization of spent chloride salt waste from pyroprocessing 153
Hierarchical simulation of aquifer heterogeneity: implications of different simulation settings on solute-transport modeling | [Simulation hiérarchique de l’hétérogénéité des aquifères: implications de différentes configurations de simulation sur la modélisation du transport de solutés] 152
Irradiated ground beef patties: Dose and dose-age estimation by volatile compounds measurement 150
Removal of lead (II) from aqueous solutions by adsorption onto activated carbons prepared from coconut shell 150
Study of an Aircraft Impact on a Nuclear Waste Interim Storage Facility: Identification of the Most Dangerous Scenario of Impact. 147
Modelling of the DYNASTY experimental facility for natural circulation under distributed heating 145
Solving the inverse problem of parameter estimation by genetic algorithms: the case of a groundwater contaminant transport model 143
Competitive sorption of some safety relevant metal ions from aqueous solution onto silica sand 142
Study of Fricke-Gel Dosimeter Calibration for Attaining Precise Measurements of the Absorbed Dose 142
Determination of parameters in groundwater contaminant transport models by means of genetic algorithms 141
COMPETITIVE SORPTION OF METAL IONS FROM AQUEOUS SOLUTION ONTO SILICA SAND 141
Preliminary analysis and design of the energy conversion system for the molten salt fast reactor 138
Application of a non-intrusive reduced order modeling approach to magnetohydrodynamics 133
Study of an Aircraft Impact on a Nuclear Waste Interim Storage Facility 133
A Monte Carlo approach to the solution of the coupled flow and transport problem in unsaturated concrete barriers 131
RAPPORTO semestrale PROGETTO EUROPEO ACSEPT - Actinide Recycling by Separation and Transmutation (Contract Number: FP7-CP-2007-211 267 period 1/3/2008-30/9/2012) HYBAR N°6 HALF YEARLY BENEFICIARY ACTIVITY REPORT POLIMI Scientific Contact: Mario Mariani, Reporting Period: 01/09/2010 - 28/02/2011 131
Monte Carlo simulation of contaminant release from a radioactive waste deposit 130
OFELIA: An OpenMC-FEniCSx coupling for neutronic calculation with temperature feedback 128
RAPPORTO semestrale PROGETTO EUROPEO ACSEPT - Actinide Recycling by Separation and Transmutation (Contract Number: FP7-CP-2007-211 267 period 1/3/2008-30/9/2012) HYBAR N°5 HALF YEARLY BENEFICIARY ACTIVITY REPORT POLIMI Scientific Contact: Mario Mariani, Reporting Period: 01/03/2010 - 31/08/2010 126
Monte Carlo simulation of nonlinear reactive contaminant transport in unsaturated porous media 125
Contaminant Transport in Experimental columns: Monte Carlo and Genetic Algorithm Approach to the Parameters Estimation. 123
RAPPORTO semestrale PROGETTO EUROPEO ACSEPT-Actinide Recycling by Separation and Transmutation (Contract Number: FP7-CP-2007-211 267) period 1/3/2008-30/9/2012) HYBAR N°4 HALF YEARLY BENEFICIARY ACTIVITY REPORT POLIMI Scientific Contact: Mario Mariani, Reporting Period: 01/09/2009-28/02/2010 123
RAPPORTO semestrale PROGETTO EUROPEO ACSEPT - Actinide Recycling by Separation and Transmutation (Contract Number: FP7-CP-2007-211 267 period 1/3/2008-30/9/2012) HYBAR N°2 HALF YEARLY BENEFICIARY ACTIVITY REPORT POLIMI, Scientific Contact: Mario Mariani, Reporting Period: 01/09/2008 - 29/02/2009 122
Non-modal stability analysis of magneto-hydrodynamic flow in a single pipe 119
RAPPORTO RICERCA DI SISTEMA ELETTRICO ENEA NNFISS – LP4 - 027 Contratto: Accordo di programma ENEA-MSE: tema di ricerca “Nuovo nucleare da fissione” Titolo: Matrici di contenimento per rifiuti radioattivi da processi pirometallurgici. http://www.enea.it/it/Ricerca_sviluppo/documenti/ricerca-di-sistema-elettrico/nuovo-nucleare-fissione/lp4/rds-90-lp4.pdf 119
RAPPORTO RICERCA DI SISTEMA ELETTRICO ENEA : NNFISS – LP2 – 099 Accordo di Programma Ministero dello Sviluppo Economico – ENEA Progetto: Nuovo nucleare da fissione. Titolo: Condizionamento di rifiuti radioattivi in Matrici vetro-ceramiche e studio delle interazioni rifiuto-terreno. http://editors.enea.it/it/Ricerca_sviluppo/documenti/ricerca-di-sistema-elettrico/nuovo-nucleare-fissione/lp2/2011/219-lp2-rds-pdf/view 219 LP2 RdS.pd 114
Monte Carlo Simulation of the effects of Different Engineered Barriers on the Diffusion of Radioactive Contaminant 111
Costruzione di modelli matematici caratterizzati da differenti funzioni obiettivo per la identificazione dei principali parametri idrogeologici di un acquifero eterogeneo. Applicazione ad un caso realistico 110
RAPPORTO semestrale PROGETTO EUROPEO ACSEPT - Actinide Recycling by Separation and Transmutation (Contract Number: FP7-CP-2007-211 267 period 1/3/2008-30/9/2012) HYBAR N°8 HALF YEARLY BENEFICIARY ACTIVITY REPORT POLIMI Scientific Contact: Mario Mariani Reporting Period: 01/09/2011 - 29/02/2012 108
Simulazione Monte Carlo della dispersione di contaminante da un deposito di rifiuti radioattivi 108
Release Of Radionuclides Following Severe Accident In Interim Storage Facility: Source Term Determination 96
Monte Carlo Simulation of Radioactive Contaminant Transport in Unsaturated Porous Media 95
Practical considerations regarding high resolution gamma spectroscopy measurements of naturally occurring radioactive samples 91
Metodologie avanzate per la valutazione della diffusione dei radionuclidi nei materiali cementizi 90
RAPPORTO semestrale PROGETTO EUROPEO ACSEPT-Actinide Recycling by Separation and Transmutation (Contract Number: FP7-CP-2007-211 267) period 1/3/2008-30/9/2012) HYBAR N°3 HALF YEARLY BENEFICIARY ACTIVITY REPORT POLIMI Scientific Contact: Mario MARIANI Reporting Period: 01/03/2009-31/08/2009 90
Simulazione Monte Carlo della dispersione di contaminante da un deposito di rifiuti radioattivi 88
RAPPORTO semestrale PROGETTO EUROPEO ACSEPT - Actinide Recycling by Separation and Transmutation (Contract Number: FP7-CP-2007-211 267 period 1/3/2008-30/9/2012) HYBAR N°7 HALF YEARLY BENEFICIARY ACTIVITY REPORT POLIMI Scientific Contact: Mario Mariani Reporting Period: 01/03/2011 - 31/08/2011 p. 1-24 88
The geostatistical approach for the restoring of pollutant release applied to experimental column data and Monte Carlo numerical tests 86
Release of Radioactive Contaminants Following an Accident in a Nuclear Waste Interim Storage Facility: Evaluation of the Radiological Impact on Population 86
Study of caesium adsorption onto alluvial sediments from the Italian Po Plain 86
Identification of aquifer parameters in transient state: The extended uniqueness of the solution 85
MONTE CARLO SIMULATION OF RADIONUCLIDES TRANSPORT THROUGH FRACTURED MEDIA 84
Monte Carlo simulation of radionuclides groundwater transport in presence of heterogeneities and nonlinearities 79
RAPPORTO semestrale PROGETTO EUROPEO ACSEPT - Actinide Recycling by Separation and Transmutation (Contract Number: FP7-CP-2007-211 267 period 1/3/2008-30/9/2012) HYBAR N°9 HALF YEARLY BENEFICIARY ACTIVITY REPORT POLIMI Scientific Contact: Mario Mariani Reporting Period: 01/03/2012 – 30/09/2012 75
Reactor dynamics analysis using Model Order Reduction: The TRIGA Mark II reactor case study 75
Stability analysis of a zero-dimensional model of PWR core using non-modal stability theory 73
TESI DI DOTTORATO in Scienza e Tecnologia negli Impanti Nucleari XIV ciclo Trasporto di contaminanti radioattivi nei mezzi porosi: modelli e prove sperimentali 71
RAPPORTO RICERCA DI SISTEMA ELETTRICO CIRTEN-POLIMI RL 1139/2010 Accordo di Programma Ministero dello Sviluppo Economico – ENEA Tema: Nuovo Nucleare da Fissione. Titolo: Analisi critica delle norme UNI inerenti la caratterizzazione radiologica dei rifiuti radioattivi http://www.enea.it/it/Ricerca_sviluppo/documenti/ricerca-di-sistema-elettrico/nuovo-nucleare-fissione/lp4/lp4-nnfiss-lp4-017.pdf 66
A Novel Parametric Dynamic Mode Decomposition Formulation: Application to Magnetohydrodynamic Liquid Metal Flows 15
Enhancing computational efficiency in nuclear fusion through reduced order modelling: Applications in magnetohydrodynamics 13
Non-modal stability analysis of magnetohydrodynamic flows for liquid metal blankets of fusion reactors 8
Photonuclear treatment for spent fuel radiotoxicity reduction: a case study investigation on minor actinides 4
Totale 11.480
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Categoria #
all - tutte 32.076
article - articoli 15.892
book - libri 0
conference - conferenze 11.876
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 776
Totale 60.620
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021139 0 0 0 0 0 0 0 0 0 0 35 104
2021/2022554 16 48 37 25 76 37 23 36 29 72 41 114
2022/2023903 91 73 33 65 101 141 13 79 144 52 72 39
2023/2024533 36 88 54 42 45 57 40 33 24 55 16 43
2024/20251.756 39 26 26 32 412 182 104 144 214 90 195 292
2025/20264.973 946 846 248 411 263 267 766 291 320 504 111 0
Totale 11.480