Phelma Formation 2022

Neutronics - 4PMGNEU1

  • Number of hours

    • Lectures 22.0
    • Projects 0
    • Tutorials 12.0
    • Internship 0
    • Laboratory works 0

    ECTS

    ECTS 2.5

Goal(s)

To learn how to use wisely the neutron diffusion approximation and how to modelize as simply as possible a nuclear reactor core for quick and easy neutronic calculations.
To prepare for more powerful tools like deterministic or stochastic transport codes.

Contact Alexis NUTTIN

Content(s)

Diffusion approximation
Slowing-down of neutrons
Criticality : condition and flux calculation
Refinements : heterogeneous, multigroup

In parallel with this lecture, the program "Neutronique en Clips" (see specific page in same semester) allows to acquire this fundamental knowledge by application on a practical case (conference article).



Prerequisites

Basic tools in mathematics and notions in nuclear physics
Introduction to nuclear reactor physics

Test

exam (2h) with a problem in 2 or 3 parts



N1 = 100% DS1
N2 = 100% DS2

Additional Information

Course list
Curriculum->Engineering degree->Semester 8

Bibliography

Lamarsh, Introduction to Nuclear Reactor Theory (1972)
Barjon, Physique des Réacteurs Nucléaires (1992)
La Neutronique, Monographie du CEA (2012)