This course is based on the course “Neutron transport theory” which has been taught at the National Research Nuclear University “MEPhI” for the past 20 years.
What you'll learn:
• Define basic processes that may occur in the reactor core, laws, equations, and the limits of applicability of models describing the neutron field in the reactor;
• Demonstrate practical experience of calculating the distribution of neutrons in media;
• Demonstrate the ability to analyze the process of slowing down neutrons in various media (typical for nuclear fission reactors) from the standpoint of understanding the physics of the process;
• Evaluate important reactor parameters including performance and safety.