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Introduction to nuclear engineering and reactor technology. [MECA2600]
[30h+30h exercises] 5 credits

Version française

Printable version

This course is taught in the 1st semester

Teacher(s):

Hamid Aït Abderrahim

Language:

French

Level:

Second cycle

>> Aims
>> Main themes
>> Content and teaching methods
>> Other information (prerequisite, evaluation (assessment methods), course materials recommended readings, ...)
>> Other credits in programs

Aims

MECA2600 is an introduction to the physical principles governing nuclear reactors.

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.

Content and teaching methods

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.

Other information (prerequisite, evaluation (assessment methods), course materials recommended readings, ...)

Pre-requisite :

- An introductory course in nuclear physics

- A basic knowledge and skill in mathematical analysis (integration, power series

expansions, ordinary and partial differential equations) as well as in numerical

computation.



References :

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.

Other credits in programs

ELME23/E

Troisième année du programme conduisant au grade d'ingénieur civil électro-mécanicien (énergie)

(5 credits)

ESP32DS/RC

Deuxième annnée du diplôme d'études spécialisées en santé publique (Contrôle physique en radioprotection)

Mandatory

MECA23

Troisième année du programme conduisant au grade d'ingénieur civil mécanicien

(5 credits)

PHYS22/G

Deuxième licence en sciences physiques

(5 credits)



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Last update :13/03/2007