NucE 409 Nuclear Materials
Course
Description
The goal of this course is to
provide students with a thorough grounding in materials relevant for nuclear
power. Students learn the relationship between microscopic damage and
macroscopic behavior. This course provides a background on the types of
materials used in nuclear reactors and their response to neutron
irradiation. Most of the materials problems encountered in the operation of
nuclear power reactors for energy production are discussed here. The
objective of the course is to give nuclear engineering students a background
in materials, so they understand the limitations put on reactor operations
and reactor design by materials performance. In the first part of the
course, we review basic concepts of physical metallurgy, to develop a
mechanistic and microstructurally based view of material properties. In the
second part of the course, we present the methods to calculate displacement
damage to the material produced by exposure to neutron irradiation. The
microstructural evolution that results from the reactor exposure (including
radiation damage and defect cluster evolution, and changes) is described.
The aim is to create a linkage between these changes at the atomistic level
and the changes in macroscopic behavior of the material. Special attention
is given to property changes that affect fuel performance and operational
safety. Both mathematical methods and experimental techniques are emphasized
so that theoretical modeling is instructed by experimental data. Students
use the TRIM and SPECTER codes to quantitatively evaluate neutron damage, as
well as learn simple analytical models that describe microstructural
evolution and property changes under irradiation.
For more details
see the Course Syllabus.
Current Course
Offering Schedule via C&DE
Semester:
SPRING 2012
Day and Time:
TBA
Location: 327
Sackett Building
Start Date:
January 9, 2012
End Date: May
4, 2012