Nuclear thermal-hydraulics (Centre d'étude nucléaire-Mol)

lbnen2001  2021-2022  Autre site

Nuclear thermal-hydraulics (Centre d'étude nucléaire-Mol)
5.00 credits
Q1
Language
English
Prerequisites
A relevant course about introduction to nuclear energy
Fundamental of fluid mechanics, heat transfer, thermodynamic

 

Learning outcomes

At the end of this learning unit, the student is able to :

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  • To learn how to estimate the volumetric heat generation rate in fission reactor cores under normal operation and shutdown conditions 
  • To learn how to analyse the thermal performance of nuclear fuel elements
  • To learn the basic fluid mechanics of single phase reactor cooling systems 
  • To learn to calculate pressure drop in reactor systems, including tube bundles, and spacer grids
  • To learn to analyse the heat transfer characteristics of single phase reactor cooling systems
  • To learn the basic fluid mechanics of two-phase systems, including modelling approaches, flow regime maps, void-quality relations, and pressure drop evaluation
  • To learn the fundamentals of boiling heat transfer, and its implications for reactor design
  • To calculate and analyze the coolant conditions throughout a reactor loop including the determination of natural convection regime
  • To learn the fundamentals of core thermal design, e.g. flow rate/pressure drop relation under different conditions (friction dominated/gravity dominated) for the evaluation of cooling performances
In addition of supervised exercises, a mini-project is organized about modelling and computing pressure drop in a boiling channel (different conditions and assumptions may be treated over the years).
 
Content
  • Thermal design principles/reactor heat generation
  • Reminders about single phase transport equations (prerequisite)
  • Two-phase flow models, transport equations
  • Thermodynamic (vessels/pressurizer) and power conversion cycle (steam)
  • Heat transfer analysis in a fuel element
  • Reminders about single phase fluid mechanics and heat transfer (prerequisite)
  • Two-phase fluid mechanics and pressure drops
  • Two-phase heat transfer (pool boiling, flow boiling)
  • ·Single heated channel (thermal and flow problems)
  • Flow loops (steady state natural convection)
Teaching methods
  • 2 t.m.: 40h teaching + seminar and 15h practical works in classroom
  • SCK.CEN guidance for demonstrations with codes
  • SCK.CEN + UCL TA for practical works
Evaluation methods
The final mark is composed of (i) a written exam(80%, closed book)including an exercise and a theoretical part, and (ii) the mini-project(20%).                                                   
Other information
Yann BARTOSIEWICZ yann.bartosiewicz@uclouvain.be
Professor at the Université Catholique de Louvain (UCL, Louvain-la-Neuve)
Master in Turbulence modeling and Transfer Phenomena, Ecole Nationale Polytechnique de Grenoble, France, 1998.
PhD in Mechanical engineering, Université de Sherbrooke, Canada, 2003: Modeling of supersonic plasma jets in non-Local Thermodynamics Equilibrium
Research fields: Fluid mechanics, heat transfer, compressible flows, two-phase flows, thermodynamics, computational fluid dynamics
Teaching duties in BNEN: Nuclear Thermal Hydraulics
Other research activities: scientific leader for UCL in European projects in nuclear thermal-hydraulics:
NURESIM: CFD Simulation of instabilities in a stratified two-phase flows relevant to PTS scenario NURISP: Simulation of two-phase chocked flows during LOCA: implementation of non-equilibrium models in CATHARE 3
THINS: Direct and Large Eddy Simulation (DNS/LES) of convective heat transfer for low Prandtl fluids (Liquid metals)
UCL Promotor of other projects in energy
Other duties: Member of the CFD group at OECD, Member of the European Nuclear Engineering Network (ENEN)
Online resources
https://www.sckcen.be/fbnen
Faculty or entity
EPL


Programmes / formations proposant cette unité d'enseignement (UE)

Title of the programme
Sigle
Credits
Prerequisites
Learning outcomes
Advanced Master in Nuclear Engineering
GNUC2MC
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