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

lmeca2648  2022-2023  Louvain-la-Neuve

Nuclear thermal-hydraulics (Centre d'étude nucléaire-Mol)
5.00 credits
40.0 h + 7.5 h
Q1
Teacher(s)
Bartosiewicz Yann;
Language
English
Main themes
  • Reactor heat generation
  •  Transport equations (single-phase & two-phase flow)
  • Thermal analysis of fuel elements
  • (Single-phase fluid mechanics and heat transfer)'usually already known
  • Two-phase flow dynamics
  • Two-phase heat transfer
  • Single heated channel; steady state analysis
  • Single heated channel; transient analysis
  • Flow loops
  • Utilisation of established codes and introduction to advanced topics (modelling and thermalhydraulics for GEN4 reactors)
Learning outcomes

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

1
  • To be familiarised with various reactor types and their main design and operational characteristics
  • 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 flow regime maps, void-quality relations, pressure drop, and critical flow
  • To learn the fundamentals of boiling heat transfer, and its implications for reactor design
  • To learn the fundamentals of core thermal design, with attention to design uncertainty analysis and hot channel factors.
 
Content
  • Lect. 1: Thermal design principles
  • Lect. 2: Reactor energy distribution
  • Lect. 3: Transport eqns. For 1-phase flow: Reminders/summary
  • Lect. 4: Tranport eqns. For 2-phase flows:basic formulation
  • Lect. 5: Tranport eqns. For 2-phase flows:equations
  • Lect. 6: Thermodynamics, cycles: non-flow and steady flow
  • Lect. 7: Thermodynamics, cycles: non steady flow first law
  • Lect. 8: Thermal analysis of fuel elements
  • Lect. 9: 1-phase fluid mechanics/heat transfer: Reminders/summary
  • Lect. 10: 2-phase fluid mechanics/pressure drops
  • Lect. 11: 2-phase fluid mechanics/pressure drops
  • Lect. 12: 2-phase heat transfer (pool boiling)
  • Lect. 13: 2-phase heat transfer (flow boiling)
  • Lect. 14: Single-heated channel: steady state analysis
Teaching methods
  • 30h of ex catedra lectures
  • 30h of partially-supervised personnal work (project)
  • 16h of supervised exercice sessions (exercice sessions)
The course takes place at the Nuclear Research Centre of Belgium (SCK.CEN) in gthe framework of the BNEN interuniversity programme (see: http://bnen.sckcen.be). 
Courses taking place at SCK.CEN are condensed over a period of 2  intensive weeks of courses.
Evaluation methods
The evaluation is a combination of continuous and in-session exam.
The continuous part is a project (team of 2) where the students have to set up a simulation tools to calculate the pressure drop (plus temperature, quality profiles) in a boiling channel under different conditions. The exam is written (in english), and assess both theoretical and practical leaning outcomes. Thus this exam is split according a theoretical part (closed book) and a practical part (opened book)
The final mark is calculated as:
  • Project + pratical part of the exam (11/20)
  • Exam (9/20)
Online resources
http://bnen.sckcen.be
Bibliography
  • Todreas, N.E. and Kazimi, M.S. Nuclear System I: Thermal Hydraulic Fundamentals, CRC Press, 2012.
  • Todreas, N. E. and Kazimi, M.S. Nuclear Systems II: Elements of Thermal Hydraulic Design, Hemisphere Publishing Corp., New York, 1990.
REFERENCE BOOKS ON THE CONTENT
  • Todreas, N.E. and Kazimi, M.S. Nuclear System I: Thermal Hydraulic Fundamentals, CRC Press, 2012. Mandatory.
  • Todreas, N. E. and Kazimi, M.S. Nuclear Systems II: Elements of Thermal Hydraulic Design, Hemisphere Publishing Corp., New York, 1990. Advised.
Teaching materials
  • Todreas, N.E. and Kazimi, M.S. Nuclear System I: Thermal Hydraulic Fundamentals, CRC Press, 2012.
  • Todreas, N. E. and Kazimi, M.S. Nuclear Systems II: Elements of Thermal Hydraulic Design, Hemisphere Publishing Corp., New York, 1990.
Faculty or entity
MECA


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

Title of the programme
Sigle
Credits
Prerequisites
Learning outcomes
Master [120] in Mechanical Engineering
MECA2M
5
Master [120] in Electro-mechanical Engineering
ELME2M
5