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Le informazioni sulla didattica, sulla ricerca e sui compiti istituzionali riportate in questa pagina sono certificate dall'Ateneo; ulteriori informazioni, redatte a cura del docente, sono disponibili sulla pagina web personale e nel curriculum vitae indicati nella scheda.
Informazioni sul docente
DocenteDi Maio Francesco
QualificaProfessore associato a tempo pieno
Dipartimento d'afferenzaDipartimento di Energia
Settore Scientifico DisciplinareING-IND/19 - Impianti Nucleari
Curriculum VitaeScarica il CV (605.25Kb - 12/03/2019)
OrcIDhttps://orcid.org/0000-0001-6659-0953

Contatti
Orario di ricevimento
DipartimentoPianoUfficioGiornoOrarioTelefonoFaxNote
----I02 - Campus LeccoLunedìDalle 16:00
Alle 17:00
----Previo appuntamento
----B12 - Campus BovisaVenerdìDalle 16:00
Alle 18:00
6372--Previo appuntamento
E-mailfrancesco.dimaio@polimi.it
Pagina web redatta a cura del docentewww.lasar.polimi.it

Fonte dati: RE.PUBLIC@POLIMI - Research Publications at Politecnico di Milano

Elenco delle pubblicazioni e dei prodotti della ricerca per l'anno 2020 (Mostra tutto | Nascondi tutto)
Tipologia Titolo Pubblicazione/Prodotto
Articoli su riviste
An efficient method for passive safety systems reliability assessment (Mostra >>)
An efficient method of key parameter screening for PCCS under SLB accident in AP1000 (Mostra >>)
Risk Analysis of Cyber-Physical Systems by GTST-MLD (Mostra >>)


Elenco delle pubblicazioni e dei prodotti della ricerca per l'anno 2019 (Mostra tutto | Nascondi tutto)
Tipologia Titolo Pubblicazione/Prodotto
Abstract in Atti di convegno
Modelling the Aging Process of a Cyber Physical System (Mostra >>)
Contributi su volumi (Capitolo o Saggio)
A non-parametric cumulative sum approach for online diagnostics of cyber attacks to nuclear power plants (Mostra >>)
Contributo in Atti di convegno
A condition-based probabilistic safety assessment framework for the estimation of the frequency of core damage due to an induced steam generator tube rupture (Mostra >>)
A dynamic safety margins estimation with a limited number of PWR large break LOCA simulations (Mostra >>)
VoI-Based Optimal Sensors Positioning and the Sub-Modularity Issue (Mostra >>)
Monografie o trattati scientifici
Stima adattiva del rischio di rottura di attrezzature in pressione, sulla base dei dati di monitoraggio (Mostra >>)
Articoli su riviste
Adversarial Risk Analysis to Allocate Optimal Defense Resources for Protecting Cyber–Physical Systems from Cyber Attacks (Mostra >>)
Condition-based probabilistic safety assessment for maintenance decision making regarding a nuclear power plant steam generator undergoing multiple degradation mechanisms (Mostra >>)


Elenco delle pubblicazioni e dei prodotti della ricerca per l'anno 2018 (Mostra tutto | Nascondi tutto)
Tipologia Titolo Pubblicazione/Prodotto
Contributi su volumi (Capitolo o Saggio)
Dynamic Accident Scenario Generation, Modeling and Post-Processing for the Integrated Deterministic and Probabilistic Safety Analysis of Nuclear Power Plants (Mostra >>)
Resilience of Cyber-Physical Systems: From Risk Modeling to Threat Counteraction (Mostra >>)
Contributo in Atti di convegno
Failure modes detection of nuclear systems using machine learning (Mostra >>)
Integrated deterministic and probabilistic safety assessment of the cooling circuit of a superconducting magnet for nuclear fusion applications (Mostra >>)
Modeling the effect of air temperature and pressure on the reliability of a passive containment cooling system (Mostra >>)
Stima adattativa del rischio di rottura di componenti in pressione soggetti a creep con un approccio probabilistico (Mostra >>)
Articoli su riviste
A Monte Carlo-based exploration framework for identifying components vulnerable to cyber threats in nuclear power plants (Mostra >>)
A Regional Sensitivity Analysis-based Expert System for safety margins control (Mostra >>)
A clustering approach for mining reliability big data for asset management (Mostra >>)
A framework for reconciliating data clusters from a fleet of nuclear power plants turbines for fault diagnosis (Mostra >>)
Condition-based probabilistic safety assessment of a spontaneous steam generator tube rupture accident scenario (Mostra >>)
Ensembles of climate change models for risk assessment of nuclear power plants (Mostra >>)
Homogeneous Continuous-Time, Finite-State Hidden Semi-Markov Modeling for Enhancing Empirical Classification System Diagnostics of Industrial Components (Mostra >>)
Hybrid Probabilistic-Possibilistic Treatment of Uncertainty in Building Energy Models: A Case Study of Sizing Peak Cooling Loads (Mostra >>)
Hybrid fuzzy-PID control of a nuclear Cyber-Physical System working under varying environmental conditions (Mostra >>)


Elenco delle pubblicazioni e dei prodotti della ricerca per l'anno 2017 (Mostra tutto | Nascondi tutto)
Tipologia Titolo Pubblicazione/Prodotto
Contributo in Atti di convegno
A Benchmark of Dynamic Reliability Methods for Probabilistic Safety Assessment (Mostra >>)
A Hybrid Monte Carlo and Possibilistic Approach to Estimate Non-Suppression Probability in Fire Probabilistic Safety Analysis (Mostra >>)
A multi-state physics modeling for estimating the size- and location-dependent loss of coolant accident initiating event probability (Mostra >>)
A sensitivity analysis for the adequacy assessment of a multi-state physics modeling approach for reliability analysis (Mostra >>)
A switching ensemble approach for remaining useful life estimation of electrolytic capacitors (Mostra >>)
Estimation of failure on-demand probability and malfunction rate values in cyber-physical systems of nuclear power plants (Mostra >>)
Local fusion of an ensemble of semi-supervised self organizing maps for post-processing accidental scenarios (Mostra >>)
Resistance-based probabilistic design by order statistics for an oil and gas deep-water well casing string affected by wear during kick load (Mostra >>)
Articoli su riviste
A Systematic Semi-Supervised Self-adaptable Fault Diagnostics approach in an evolving environment (Mostra >>)
A hierarchical decision-making framework for the assessment of the prediction capability of prognostic methods (Mostra >>)
A locally adaptive ensemble approach for data-driven prognostics of heterogeneous fleets (Mostra >>)
Determination of prime implicants by differential evolution for the dynamic reliability analysis of non-coherent nuclear systems (Mostra >>)
Optimization of a dynamic uncertain causality graph for fault diagnosis in nuclear power plant (Mostra >>)
Postprocessing of Accidental Scenarios by Semi-Supervised Self-Organizing Maps (Mostra >>)
Prediction of industrial equipment Remaining Useful Life by fuzzy similarity and belief function theory (Mostra >>)
Safety margin sensitivity analysis for model selection in nuclear power plant probabilistic safety assessment (Mostra >>)
Three-loop Monte Carlo simulation approach to Multi-State Physics Modeling for system reliability assessment (Mostra >>)


Elenco delle pubblicazioni e dei prodotti della ricerca per l'anno 2016 (Mostra tutto | Nascondi tutto)
Tipologia Titolo Pubblicazione/Prodotto
Contributo in Atti di convegno
A Repairable Dynamic Event Tree for the safety assessment of a steam generator of a nuclear power plant (Mostra >>)
A Semi-Supervised Self Organizing Map for Post-Processing the Scenarios of an Integrated Deterministic and Probabilistic Safety Analysis (Mostra >>)
A semi-supervised feature selection approach for fault diagnostics in evolving environments (Mostra >>)
Comparison of Dynamic Reliability Methods for Probabilistic Safety Assessment (Mostra >>)
Fire compartment partitioning approaches for fire probabilistic safety analysis of a high-temperature gas-cooled reactor (Mostra >>)
Optimization of a Dynamic Uncertain Causality Graph (DUCG) for Fault Diagnostics in Nuclear Power Plants by Genetic Algorithm (Mostra >>)
Prediction capability assessment of data-driven prognostic methods for railway industry by an in-depth-quality-control strategy (Mostra >>)
Articoli su riviste
A dynamic probabilistic safety margin characterization approach in support of Integrated Deterministic and Probabilistic Safety Analysis (Mostra >>)
An approach based on Support Vector Machines and a K-D Tree search algorithm for identification of the failure domain and safest operating conditions in nuclear systems (Mostra >>)
Bootstrapped-ensemble-based Sensitivity Analysis of a trace thermal-hydraulic model based on a limited number of PWR large break loca simulations (Mostra >>)
Component- and system-level degradation modeling of digital Instrumentation and Control systems based on a Multi-State Physics Modeling Approach (Mostra >>)
Hierarchical k-nearest neighbours classification and binary differential evolution for fault diagnostics of automotive bearings operating under variable conditions (Mostra >>)
Improving scheduled maintenance by missing data reconstruction: A double-loop Monte Carlo approach (Mostra >>)
Invariant methods for an ensemble-based sensitivity analysis of a passive containment cooling system of an AP1000 nuclear power plant (Mostra >>)
Online Performance Assessment Method for a Model-Based Prognostic Approach (Mostra >>)
Remaining useful life estimation in heterogeneous fleets working under variable operating conditions (Mostra >>)
Transient identification by clustering based on Integrated Deterministic and Probabilistic Safety Analysis outcomes (Mostra >>)
manifesti v. 3.3.7 / 3.3.7
Area Servizi ICT
29/05/2020