NUE 301
Nuclear Materials
3
Course Description
On completion, the student should be able to:
1. freely discuss using the right terminologies, the mechanical and atomic properties of
materials used in nuclear reactors;
2. describe the reactor fuel fabrication process starting with uranium dioxide pellets,
cladding, fuel pin and fuel bundles;
3. identify how radiation affects materials used in nuclear reactors;
4. describe how fission affects swelling and release of nuclear materials;
5. analyse engineered barriers for the containment of fusion products;
6. explain how structural alloys are damaged by neutrons and suggest method(s) of
reducing this damage; and
7. explain the properties and how uranium dioxide fuels are fabricated.
Course Outline
Effects of irradiation on the atomic and mechanical properties of materials in nuclear reactors.
Materials for cladding, fuel rods and bundles. Fission product swelling and release; neutron
damage to structural alloys; fabrication and properties of uranium dioxide fuel.