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PORTALE DELLA DIDATTICA

Development of Generation-IV Lead-cooled Fast Reactors (LFR) (didattica di eccellenza)

01TZBIV, 01TZBIV

A.A. 2018/19

Lingua dell'insegnamento

Inglese

Corsi di studio

Dottorato di ricerca in Energetica - Torino

Organizzazione dell'insegnamento
Didattica Ore
Docenti
Docente Qualifica Settore h.Lez h.Es h.Lab h.Tut Anni incarico
Dulla Sandra Professore Ordinario ING-IND/18 0 0 0 0 1
Dulla Sandra Professore Ordinario ING-IND/18 2 0 0 0 1
Collaboratori
Espandi

Didattica
SSD CFU Attivita' formative Ambiti disciplinari
*** N/A ***    
2018/19
PERIOD: MAY Dr. M. Sarotto e Ing. G. Grasso - ENEA In the framework of the R&D activities regarding Generation-IV nuclear reactors, Italy holds a technological leadership position in Europe for what concerns Lead cooled Fast Reactors (LFR). Italian activities in this field include both the participation to international research projects (EURATOM, IAEA, OECD-NEA, etc.), as well as national activities, financially supported by the Ministry for the Economic Development through the “Ricerca di Sistema Elettrico” and developed by ENEA, ANSALDO and CIRTEN. All these efforts have been focused on the design of the demonstrator reactor ALFRED (Advanced LFR European Demonstrator), which is supposed to be constructed (within the framework of EC projects) by 2030 in the Pitesti site (Romania). Starting from the basic aspects related to neutronics, thermal-hydraulics and thermomechanics, the computational tools, currently being developed, validated and adopted in support to core design, will be described: • Neutronic codes, deterministic and Monte Carlo; • Thermal-hydraulic codes for sub-channel and fuel elements; • Thermomechanic code for the fuel pin. In the frame of innovative system cooled by liquid lead, the specificities related to subcritical source-driven system ADS (Accelerator Driven Systems), developed to the aim of transmuting minor actinides (Am, Np, Cm), will be addressed.
PERIOD: MAY Dr. M. Sarotto e Ing. G. Grasso - ENEA In the framework of the R&D activities regarding Generation-IV nuclear reactors, Italy holds a technological leadership position in Europe for what concerns Lead cooled Fast Reactors (LFR). Italian activities in this field include both the participation to international research projects (EURATOM, IAEA, OECD-NEA, etc.), as well as national activities, financially supported by the Ministry for the Economic Development through the “Ricerca di Sistema Elettrico” and developed by ENEA, ANSALDO and CIRTEN. All these efforts have been focused on the design of the demonstrator reactor ALFRED (Advanced LFR European Demonstrator), which is supposed to be constructed (within the framework of EC projects) by 2030 in the Pitesti site (Romania). Starting from the basic aspects related to neutronics, thermal-hydraulics and thermomechanics, the computational tools, currently being developed, validated and adopted in support to core design, will be described: • Neutronic codes, deterministic and Monte Carlo; • Thermal-hydraulic codes for sub-channel and fuel elements; • Thermomechanic code for the fuel pin. In the frame of innovative system cooled by liquid lead, the specificities related to subcritical source-driven system ADS (Accelerator Driven Systems), developed to the aim of transmuting minor actinides (Am, Np, Cm), will be addressed.
The proposed course will deal with the more fundamental aspects regarding the core design of LFR, illustrating the potentialities of such a system (e.g, sustainability, safety and economy) and dealing in a systematic way with the issues arising mainly with material properties.
The proposed course will deal with the more fundamental aspects regarding the core design of LFR, illustrating the potentialities of such a system (e.g, sustainability, safety and economy) and dealing in a systematic way with the issues arising mainly with material properties.
A background in energy engineering and nuclear technologies is preferred
A background in energy engineering and nuclear technologies is preferred
1) GENERATION IV LEAD COOLED FAST REACTOR: ALFRED Demonstrator - Gen-IV objectives - Motivation of LFR technology development - Objectives of ALFRED demonstrator in the European context - Italian contribution to ALFRED - ALFRED Conceptual design - Structural materials and coolant chemistry issues 2) FUNDAMENTALS OF FAST REACTOR NEUTRONICS - General characteristics and history of fast neutron reactors - Fast reactor core neutronics main properties and issues - Integral parameters and feedback reactivity coefficients - Deterministic and stochastic computational tools for neutronics 3) NEUTRONIC ANALYSIS: ALFRED CORE CASE STUDY - Steady-state reactor core characterization - Feedback coefficients and integral parameter evaluation - The ERANOS deterministic code: modules (cell and full-core capability), calculation modes (flux/power, burn up, spectral indexes), post-processing tools developed at ENEA (VisualCore, VisualPin) - Validation of deterministic (ERANOS) and Monte Carlo (MCNP and Serpent) models 4) FAST REACTOR THERMALHYDRAULICS - Fundamentals of fast reactor thermal-hydraulics (TH) - Computational tools for TH: system codes, sub-channel codes, CFD codes - ENEA experimental facilities for TH code validation 5) CORE DESIGN - General introduction to the design problem - Iteration between design and verification - Holistic approach to design and its phases - ALFRED and ELFR case studies - Role of Design-Oriented Codes (DOC) and Verification-Oriented Codes (VOC) 6) CONCEPTUAL DESIGN AND ANALYSIS OF ACCELERATOR-DRIVEN SYSTEMS – ADS (1h) - The EFIT case study - ABAQUS: a multi-dimensional representation of multiphysics parameters 7) CORE AND FUEL ASSEMBLY TH ANALYSYS (2 h) - Computational tools developed at ENEA for fast reactor TH: - ANTEO+ (ANalisi TErmoidraulica Ottimizzata): sub-assembly TH code - TIFONE (TermoIdraulica delle Fughe che Occorrono nel Nocciolo fra gli Elementi): bypass flow modelling aspects and sub-assembly approach 8) FUNDAMENTALS OF FAST REACTOR THERMOMECHANICS (1 h) - Introduction to core thermomechanical behavior and main issues, - Objectives and guidelines for thermomechanical design 9) THERMOMECHANICAL (TM) ANALYSIS (2 h) - Models for the TM characterization at the system, core, fuel assembly and pin level - Codes developed at ENEA for TM analysis: -TEMIDE (TErmoMeccanica Improntata al Design dell’Elemento di combustibile): codes based on engineering correlations to support pin design; - TEIA (Termomeccanica Estesa all’Intero Assemblaggio): code for the TM analysis of the assembly-casing interaction; - FEBE (Fiorescenza degli Elementi fra i Blocchi Esterni): code for the study of the TM core behavior to support the Core Restraint System design.
1) GENERATION IV LEAD COOLED FAST REACTOR: ALFRED Demonstrator - Gen-IV objectives - Motivation of LFR technology development - Objectives of ALFRED demonstrator in the European context - Italian contribution to ALFRED - ALFRED Conceptual design - Structural materials and coolant chemistry issues 2) FUNDAMENTALS OF FAST REACTOR NEUTRONICS - General characteristics and history of fast neutron reactors - Fast reactor core neutronics main properties and issues - Integral parameters and feedback reactivity coefficients - Deterministic and stochastic computational tools for neutronics 3) NEUTRONIC ANALYSIS: ALFRED CORE CASE STUDY - Steady-state reactor core characterization - Feedback coefficients and integral parameter evaluation - The ERANOS deterministic code: modules (cell and full-core capability), calculation modes (flux/power, burn up, spectral indexes), post-processing tools developed at ENEA (VisualCore, VisualPin) - Validation of deterministic (ERANOS) and Monte Carlo (MCNP and Serpent) models 4) FAST REACTOR THERMALHYDRAULICS - Fundamentals of fast reactor thermal-hydraulics (TH) - Computational tools for TH: system codes, sub-channel codes, CFD codes - ENEA experimental facilities for TH code validation 5) CORE DESIGN - General introduction to the design problem - Iteration between design and verification - Holistic approach to design and its phases - ALFRED and ELFR case studies - Role of Design-Oriented Codes (DOC) and Verification-Oriented Codes (VOC) 6) CONCEPTUAL DESIGN AND ANALYSIS OF ACCELERATOR-DRIVEN SYSTEMS – ADS (1h) - The EFIT case study - ABAQUS: a multi-dimensional representation of multiphysics parameters 7) CORE AND FUEL ASSEMBLY TH ANALYSYS (2 h) - Computational tools developed at ENEA for fast reactor TH: - ANTEO+ (ANalisi TErmoidraulica Ottimizzata): sub-assembly TH code - TIFONE (TermoIdraulica delle Fughe che Occorrono nel Nocciolo fra gli Elementi): bypass flow modelling aspects and sub-assembly approach 8) FUNDAMENTALS OF FAST REACTOR THERMOMECHANICS (1 h) - Introduction to core thermomechanical behavior and main issues, - Objectives and guidelines for thermomechanical design 9) THERMOMECHANICAL (TM) ANALYSIS (2 h) - Models for the TM characterization at the system, core, fuel assembly and pin level - Codes developed at ENEA for TM analysis: -TEMIDE (TErmoMeccanica Improntata al Design dell’Elemento di combustibile): codes based on engineering correlations to support pin design; - TEIA (Termomeccanica Estesa all’Intero Assemblaggio): code for the TM analysis of the assembly-casing interaction; - FEBE (Fiorescenza degli Elementi fra i Blocchi Esterni): code for the study of the TM core behavior to support the Core Restraint System design.
Luogo: Aula Cafaro, DENERG department, entrance door 5, third floor Docenti Dr. Giacomo Grasso (ENEA, Bologna) Dr. Massimo Sarotto (ENEA Saluggia) ORARIO DETTAGLIATO Monday May 6th: 9.30-12.30 and 14-17 Tuesday May 7th: 10.00-13.00 and 14.30-16.30 Wednesday May 8th: 10.00-13.00 and 14.30-16.30
Luogo: Aula Cafaro, DENERG department, entrance door 5, third floor Docenti Dr. Giacomo Grasso (ENEA, Bologna) Dr. Massimo Sarotto (ENEA Saluggia) ORARIO DETTAGLIATO Monday May 6th: 9.30-12.30 and 14-17 Tuesday May 7th: 10.00-13.00 and 14.30-16.30 Wednesday May 8th: 10.00-13.00 and 14.30-16.30
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