Skip to content
BRIDGE BRIDGE Diaspora BRIDGE
NUE 304

Introduction to Nuclear Reactor Theory

Engineering and Technology
B.Eng. Nuclear Engineering
3
Course Description
At the end of this course, students should be able to 1. describe the neutron generation and transport reactor core principles 2. explain the concept of thermalizing of fast neutrons and resonance absorptions; 3. Learn the neutron diffusion theory; 4. Learn the multiplication factors and criticality and the effect of delayed neutrons; 5. define basic reactor terms such as neutron interaction, nuclear fission, chain; and reaction; 6. describe the different types of reactors; 7. calculate critical concentrations, mass and dimensions; 8. relate the reactor core basic systems and components as well as be able to solve core design problem; 9. Use of relevant computer codes for criticality studies and reactor control; and 10. describe reactor dynamics.
Course Outline
Neutron interactions, nuclear fission, and chain reacting systematics in thermal and fast nuclear reactors. Diffusion and slowing down of neutrons. Criticality condition and calculations of critical concentrations, mass and dimensions, core design problems, computer methods and applications, few-group approximation, and point kinetics. Nuclear reactor dynamics and reactivity feedbacks.
0 Total Views

Made Possible Through

Federal Ministry of Education
TETFund