Nuclear Reactor Thermal Hydraulics

3 credits · Undergraduate

An introduction to nuclear reactor thermal hydraulics will be provided. Fundamental concepts of multiphase flow and interfacial phenomena will be introduced. Gas-liquid two-phase flow will be examined with a focus on flow regimes and pressure drop. Pool boiling and flow boiling will be examined including concepts such as subcooled boiling, nucleate boiling, critical heat flux, dryout, and rewetting. Reactor types will also be introduced, and the course content will be complemented by laboratory exercises.