logo-polimi
Loading...
Degree programme
Programme Structure
Show/Search Programme
Degree Programme
International context
Customized Schedule
Your customized time schedule has been disabled
Enable
Search
Search a Professor
Professor's activities
Search a Course
Search a Course (system prior D.M. n. 509)
Search Lessons taught in English
Information on didactic, research and institutional assignments on this page are certified by the University; more information, prepared by the professor, are available on the personal web page and in the curriculum vitae indicated on this webpage.
Information on professor
ProfessorDi Maio Francesco
QualificationAssociate professor
Belonging DepartmentDipartimento di Energia
Scientific-Disciplinary SectorING-IND/19 - Nuclear Power Plants
Curriculum VitaeDownload CV (605.25Kb - 12/03/2019)
OrcIDhttps://orcid.org/0000-0001-6659-0953

Contacts
Professor's office hours
DepartmentFloorOfficeDayTimetableTelephoneFaxNotes
----I02 - Campus LeccoMondayFrom 16:00
To 17:00
----Previo appuntamento
----B12 - Campus BovisaFridayFrom 16:00
To 18:00
6372--Previo appuntamento
E-mailfrancesco.dimaio@polimi.it
Professor's personal websitewww.lasar.polimi.it

Data source: RE.PUBLIC@POLIMI - Research Publications at Politecnico di Milano

List of publications and reserach products for the year 2020
No product yet registered in the year 2020


List of publications and reserach products for the year 2019 (Show all details | Hide all details)
Type Title of the Publicaiton/Product
Journal Articles
Condition-based probabilistic safety assessment for maintenance decision making regarding a nuclear power plant steam generator undergoing multiple degradation mechanisms (Show >>)
Adversarial Risk Analysis to Allocate Optimal Defense Resources for Protecting Cyber–Physical Systems from Cyber Attacks (Show >>)
Contributions on scientific books
A non-parametric cumulative sum approach for online diagnostics of cyber attacks to nuclear power plants (Show >>)
Scientific Books
Stima adattiva del rischio di rottura di attrezzature in pressione, sulla base dei dati di monitoraggio (Show >>)
Conference proceedings
A dynamic safety margins estimation with a limited number of PWR large break LOCA simulations (Show >>)
A condition-based probabilistic safety assessment framework for the estimation of the frequency of core damage due to an induced steam generator tube rupture (Show >>)


List of publications and reserach products for the year 2018 (Show all details | Hide all details)
Type Title of the Publicaiton/Product
Journal Articles
A Monte Carlo-based exploration framework for identifying components vulnerable to cyber threats in nuclear power plants (Show >>)
A clustering approach for mining reliability big data for asset management (Show >>)
Homogeneous Continuous-Time, Finite-State Hidden Semi-Markov Modeling for Enhancing Empirical Classification System Diagnostics of Industrial Components (Show >>)
Condition-based probabilistic safety assessment of a spontaneous steam generator tube rupture accident scenario (Show >>)
A Regional Sensitivity Analysis-based Expert System for safety margins control (Show >>)
Hybrid fuzzy-PID control of a nuclear Cyber-Physical System working under varying environmental conditions (Show >>)
Ensembles of climate change models for risk assessment of nuclear power plants (Show >>)
A framework for reconciliating data clusters from a fleet of nuclear power plants turbines for fault diagnosis (Show >>)
Hybrid Probabilistic-Possibilistic Treatment of Uncertainty in Building Energy Models: A Case Study of Sizing Peak Cooling Loads (Show >>)
Contributions on scientific books
Dynamic Accident Scenario Generation, Modeling and Post-Processing for the Integrated Deterministic and Probabilistic Safety Analysis of Nuclear Power Plants (Show >>)
Resilience of Cyber-Physical Systems: From Risk Modeling to Threat Counteraction (Show >>)
Conference proceedings
Integrated deterministic and probabilistic safety assessment of the cooling circuit of a superconducting magnet for nuclear fusion applications (Show >>)
Failure modes detection of nuclear systems using machine learning (Show >>)
Stima adattativa del rischio di rottura di componenti in pressione soggetti a creep con un approccio probabilistico (Show >>)
Modeling the effect of air temperature and pressure on the reliability of a passive containment cooling system (Show >>)


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


List of publications and reserach products for the year 2016 (Show all details | Hide all details)
Type Title of the Publicaiton/Product
Journal Articles
Remaining useful life estimation in heterogeneous fleets working under variable operating conditions (Show >>)
Hierarchical k-nearest neighbours classification and binary differential evolution for fault diagnostics of automotive bearings operating under variable conditions (Show >>)
Component- and system-level degradation modeling of digital Instrumentation and Control systems based on a Multi-State Physics Modeling Approach (Show >>)
Bootstrapped-ensemble-based Sensitivity Analysis of a trace thermal-hydraulic model based on a limited number of PWR large break loca simulations (Show >>)
Invariant methods for an ensemble-based sensitivity analysis of a passive containment cooling system of an AP1000 nuclear power plant (Show >>)
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 (Show >>)
Transient identification by clustering based on Integrated Deterministic and Probabilistic Safety Analysis outcomes (Show >>)
A dynamic probabilistic safety margin characterization approach in support of Integrated Deterministic and Probabilistic Safety Analysis (Show >>)
Improving scheduled maintenance by missing data reconstruction: A double-loop Monte Carlo approach (Show >>)
Online Performance Assessment Method for a Model-Based Prognostic Approach (Show >>)
Conference proceedings
Optimization of a Dynamic Uncertain Causality Graph (DUCG) for Fault Diagnostics in Nuclear Power Plants by Genetic Algorithm (Show >>)
A semi-supervised feature selection approach for fault diagnostics in evolving environments (Show >>)
Prediction capability assessment of data-driven prognostic methods for railway industry by an in-depth-quality-control strategy (Show >>)
Comparison of Dynamic Reliability Methods for Probabilistic Safety Assessment (Show >>)
A Semi-Supervised Self Organizing Map for Post-Processing the Scenarios of an Integrated Deterministic and Probabilistic Safety Analysis (Show >>)
A Repairable Dynamic Event Tree for the safety assessment of a steam generator of a nuclear power plant (Show >>)
Fire compartment partitioning approaches for fire probabilistic safety analysis of a high-temperature gas-cooled reactor (Show >>)
manifesti v. 3.2.3 / 3.2.3
Area Servizi ICT
17/02/2020