CH EN 512
Nuclear Reactor Transient Modeling
Chemical Engineering
Ira A. Fulton College of Engineering
Course Description
This course focuses on the thermal-hydraulic assessment of nuclear reactor design basis and beyond design basis transients using state-of-the-art computer code. Instruction will focus on both instruction in using this code and study of design basis accidents for both standard and advanced reactor concepts.
When Taught
Contact Department
Grade Rule
Grade Rule 8: A, B, C, D, E, I (Standard grade rule)
Min
3
Fixed
3
Fixed
3
Fixed
0
Other Prerequisites
or equivalent to CH EN 374
Recommended
CH EN 376
