NucE 597D Nuclear Reactor Safety
Course
Description
The Nuclear Reactor Safety course
will examine the basis for reactor safety in commercial power plants; and
the role of the NRC, utility, and the reactor designer, in determining the
safety of the plant. The safety systems which have been installed on plants
will be discussed as well as the postulated accidents, and their
classification, which are used to verify that the plant design is
sufficiently robust and will meet the licensing criteria. Different types of
accident transients will be discussed and the analysis of these transients.
The two principal accidents which have occurred, TMI and Chernobyl will be
discussed in detail as well as other accidents or abnormal reactor
operational behavior and incidents that have occurred. Advanced Light Water
Reactor designs which feature enhanced safety will also be discussed
For more details
see the Course Syllabus.
Current Course
Offering Schedule via C&DE
Spring 2007
Day and Time:
Monday and Wednesday, 5:00 to 7:00 PM
Location:
307 Hammond Building
Start Date: January
16, 2007
End Date: May 11,
2007