CHEN 464 - Nuclear Fluid Mechanics and Heat Transfer

When Offered: F, S, SS

3 Credit(s)
3 Lecture Hour(s)
0 Lab Hour(s)

This course provides discussions of thermal hydraulic characteristics of power reactors, thermal design principles, reactor heat generation, transport equations for single phase flow and two-phase flow. Analyses of fuel elements, two phase flow dynamics, two phase heat transfer, single heated channels, steady state flow and heat transfer analysis are given.

Prerequisite(s): Senior standing in CHEN or consent of instructor.