NUE 401
Nuclear Reactor Thermal-hydraulics
2
Course Description
At the end of this course, students should be able to
1. describe and quantify the sources of energy production and transfer parameters;
2. describe the heat and mass transfer flow characteristics of power reactors;
3. explain and use transport equations for single and two phase flows;
4. calculate the heat transfer and pressure losses;
5. perform thermal analysis of fuel elements; and
6. formulate and solve of the reactor thermal hydraulic design problems.
Course Outline
Nuclear system heat transfer and fluid flow; convection in single and two phase flow; liquid
metal heat transfer, pressure loss calculations; fuel element design and heat transfer; thermal-
hydraulics design of nuclear systems; thermal stress analysis.