Introduction to nuclear engineering and reactor technology

lmeca2600  2021-2022  Louvain-la-Neuve

Introduction to nuclear engineering and reactor technology
5.00 credits
30.0 h + 30.0 h
Q1
Teacher(s)
Aït Abderrahim Hamid;
Language
English
Main themes
An introductory course in nuclear physics. Some basic knowledge and skill in mathematical analysis (integration, power series expansions, ordinary and partial differential equations) as well as in numerical computation. The aim of this course is threefold: a description of the basic principles of nuclear engineering (fuel cycles, reactor types, etc ...), the understanding of the fundsamental concepts (cross sections, phase space, neutron fluxes and currents, criticality, etc...) and the development of a model (the multigroup-diffusion model) allowing to perform reactor computations. By reactor computations, one generally refers to the determination of the conditions that have to be satisfied in order to produce energy in steady-state, the space dependence of the energy production inside the reactor and the time evolution of the energy production if the steady-state conditions are no longer met. The MECA2600 course is adapted from the reference "Nuclear Reactor Analysis", by J.J. Duderstadt and L.J. Hamilton (John Wiley, 1976), chapters 1 to 6.
Learning outcomes

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

1 In consideration of the reference table AA of the program "Masters degree in Mechanical Engineering", this course contributes to the development, to the acquisition and to the evaluation of the following experiences of learning:
  • AA1.1, AA1.2, AA1.3
  • AA2.1, AA2.4, AA2.5
  • AA3.1, AA3.3
  • AA5.1, AA5.4, AA5.5
  • AA6.1, AA6.2
MECA2600 is an introduction to the physical principles governing nuclear reactors
 
Content
MECA2600 is an introduction to the physical principles governing nuclear reactors. The aim of this course is threefold: a description of the basic principles of nuclear engineering (fuel cycles, reactor types, etc ...), the understanding of the fundsamental concepts (cross sections, phase space, neutron fluxes and currents, criticality, etc...) and the development of a model (the multigroup-diffusion model) allowing to perform reactor computations. By reactor computations, one generally refers to the determination of the conditions that have to be satisfied in order to produce energy in steady-state, the space dependence of the energy production inside the reactor and the time evolution of the energy production if the steady-state conditions are no longer met.
Bibliography
Le cours MECA 2600 est donné à partir du livre "Nuclear Reactor Analysis" de J.J. Duderstadt et L.J. Hamilton (John Wiley, 1976), chapitres 1 à 6 inclus.
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

Master [120] in Electro-mechanical Engineering

Master [120] in Physics

Certificat universitaire de contrôle physique en radioprotection (Classe I)