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.
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)