Nuclear thermal-hydraulics.

6 credits

40.0 h + 7.5 h

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)

Aims

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.

The contribution of this Teaching Unit to the development and command of the skills and learning outcomes of the programme(s) can be accessed at the end of this sheet, in the section entitled “Programmes/courses offering this Teaching Unit”.

Content

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)

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

The course takes place at the Nuclear Research Centre of Belgium (SCK.CEN) in gthe framework of the BNEN interuniversity programme (see: http://www3.sckcen.be/bnen/). One makes use of the software available at the research centre.
Courses taking place at SCK.CEN are condensed over a period of 1 to 3 intensive weeks of courses, according to the number of ECTS.

Evaluation methods

Closed book - oral

Online resources

http://icampus.uclouvain.be/claroline/course/index.php?cid=MECA2648

Bibliography

REFERENCE BOOKS ON THE CONTENT

Todreas, N.E. and Kazimi, M.S. Nuclear System I: Thermal Hydraulic Fundamentals, Hemisphere Publishing Corp., New York, 1990
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

Aims

Master [120] in Electro-mechanical Engineering

ELME2M

Master [120] in Mechanical Engineering

MECA2M