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Scheda Riassuntiva
Anno Accademico 2014/2015
Scuola Scuola di Ingegneria Industriale e dell'Informazione
Insegnamento 093571 - FISICA DEI MATERIALI NUCLEARI + ADVANCED THERMAL HYDRAULICS AND SAFETY OF NUCLEAR REACTORS
  • 093569 - ADVANCED THERMAL HYDRAULICS AND SAFETY OF NUCLEAR REACTORS
Docente Ninokata Hisashi
Cfu 5.00 Tipo insegnamento Modulo Di Corso Strutturato


Programma dettagliato e risultati di apprendimento attesi

 

2014/2015 Syllabus of “Advanced Thermal Hydraulics And Safety of Nuclear Reactors” the ATHANS Course (5 credits)  

  1. introduction: nuclear reactors and thermal hydraulics design (to identify the important issues to address and to explore in this course);
  2. nuclear power plant accidents at TMI, Chernobyl, and Fukushima - reflections and lessons learned;
  3. review of reactor physics fundamentals: eigenvalue problems, reactor kinetics and applications of perturbation theory [Exercises];(to better understand nuclear reactor safety);
  4. fundamentals of momentum and energy transfer mechanisms and modeling;
  5. nuclear reactor fuel and core design fundamentals: single-phase flow pressure drops, heat transfer coefficients, mass and energy integral balances; hot spot factors and uncertainties; self-controllability concept of nuclear reactors [Exercises] (to better understand importance of coupled nuclear and thermal hydraulics phenomena over reactor safety);
  6. homogeneous equilibrium two-phase flow model (HEM), two-phase flow pressure drops and heat transfer coefficients [Exercises]; critical heat flux; analysis of boiling two-phase flow natural circulation capability [Exercises] (to understand macroscopic behaviors of the nuclear plant system);
  7. derivation of two-fluid two-phase flow model governing equations and constitutive equations; relationships among flow quality, slip ratio, void fraction, wall-shear and inter-phase shear stresses [Exercises];
  8. introduction to numerical solution methods: finite difference methods of heat conduction and convection-diffusion Burger equations;accuracy, numerical diffusion and instabilities; von Neumann instability analysis [Exercises]; 
  9. overview of computational fluid dynamics (CFD) and distributed parameter approach (RANS, LES, DNS); lumped parameter approach;CFD pros/cons;
  10. subchannel analysis: lumped parameter approach in 2D and 3D single-phase flows and for boiling two-phase flows in rod bundles; distributed resistance model (DRM), turbulent mixing and global flow pulsation phenomena; importance of physical models; [Exercises]; interrelationship between lumped and distributed parameter approaches and hierarchy of numerical methods - an overall view;
  11. nuclear safety goal, targets and requirements; safety design in terms of deterministic concepts and defence-in-depth principle; safety evaluation by deterministic approach and probabilistic risk concepts, based on the lessons from the Fukushima nuclear accidents;
  12. introduction to Probabilistic Safety Assessment (PSA) - concepts and a glimpse at actual practices [Exercises];
  13. [special topics: contingency] thermal hydraulics & safety of sodium-cooled fast reactor and comparison with those of light water reactors.

=========== Comments ===========

In principle, this course is a continuation of the course “Nuclear Reactor Plants” by Professor Antonio Cammi in the 2013/2014 second semester. Some of the topics will be repeated briefly and quickly on behalf of those who did not take the course.

Lecture will be delivered based on hand-outs notes in PDF available either on a dropbox or Beep (Be-ePoli), which is under preparation, as of September 15. Students will be informed of the procedure how to access and download the material in the first lecture on October 13 (Monday), 2014.

Thermal hydraulics is one of the most important constituents of extremely complex nuclear reactor system design and safety. In this course, you are assumed to have fundamental knowledge on reactor physics and thermo-hydraulics as pre-requisites.

By the end of the semester, you shall learn a wide spectrum of nuclear reactor engineering and be well equipped with good knowledge on nuclear energy technology, with an ability to make your own judgement on how safe your nuclear reactors are.

Communication between teacher and students is most respected. I would put the highest priority on the enhancement of your understanding the contents. Therefore I am willing to talk and adjust based on your knowledge levels whenever necessary. In my capacity of teaching I try let none of you feel left behind during the session. I appreciate any kinds of questions during the class. Welcome to ATHANS!!

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Informazioni in lingua inglese a supporto dell'internazionalizzazione
Insegnamento erogato in lingua Inglese
Disponibilità di materiale didattico/slides in lingua inglese
Disponibilità di libri di testo/bibliografia in lingua inglese
Possibilità di sostenere l'esame in lingua inglese
Disponibilità di supporto didattico in lingua inglese
schedaincarico v. 1.7.2 / 1.7.2
Area Servizi ICT
04/10/2022