Number of hours
- Lectures 30.0
- Projects 0
- Tutorials 14.0
- Internship 0
- Laboratory works 0
ECTS
ECTS 4.0
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.
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).
Contact Nicolas CAPELLAN, Alexis NUTTINContent(s)
Diffusion approximation
Slowing-down of neutrons
Criticality : condition and flux calculation
Refinements : heterogeneous, multigroup
Prerequisites
UE Physics 1
UE Reactor Physics 1
Basic tools in mathematics and notions in nuclear physics
Introduction to nuclear reactor physics
Test
standard paper exam (2h) for neutronics
group presentation (1/2h per group) for the clip part
- Calculator allowed
- One double-sided note sheet allowed
Bibliography
Lamarsh, Introduction to Nuclear Reactor Theory (1972)
Barjon, Physique des Réacteurs Nucléaires (1992)
La Neutronique, Monographie du CEA (2012)