Physics of Nuclear Reactors (EPFL)

Abstract

In this course, one acquires an understanding of the basic neutronics interactions occurring in a nuclear fission reactor and, as such, the conditions for establishing and controlling a nuclear chain reaction.

Objective

By the end of the course, the student must be able to: - Elaborate on neutron diffusion equation - Systematize nuclear reaction cross sections - Formulate approximations to solving the diffusion equation for simple systems

Content

Content: - Brief review of nuclear physics - Historical: Constitution of the nucleus and discovery of the neutron - Nuclear reactions and radioactivity - Cross sections - Differences between fusion and fission. - Nuclear fission - Characteristics - Nuclear fuel - Introductory elements of neutronics. - Fissile and fertile materials - Breeding. - Neutron diffusion and slowing down - Monoenergetic neutrons - Angular and scalar flux - Diffusion theory as simplified case of transport theory - Neutron slowing down through elastic scattering. - Multiplying media (reactors) - Multiplication factors - Criticality condition in simple cases. - Thermal reactors - Neutron spectra - Multizone reactors - Multigroup theory and general criticality condition - Heterogeneous reactors. - Reactor kinetics - Point reactor model: prompt and delayed transients - Practical applications. - Reactivity variations and control - Short, medium and long term reactivity changes ? Different means of control.

Resources