Thermal-Hydraulic Design of Nuclear Reactors

MANE-6370

An introduction to the principles underlying the thermal-hydraulic design of nuclear power reactors. Topics include plant thermal limits, sub-channel analysis, thermal-hydraulic stability analysis, and reactor system response during both normal and postulated accident conditions.

3 credits
Prereqs:
none

Past Term Data

Offered
Not Offered
Offered as Cross-Listing Only
No Term Data
Spring Summer Fall
(Session 1) (Session 2)
2023
2022
2021
2020
Thermal-hydr Dsgn Nuc Rc (3c)
  • Michael Podowski
Seats Taken: 2/15
2019
2018
2017
2016
Thermal-hydr Dsgn Nuc Rc (3c)
  • Michael Podowski
Seats Taken: 8/30
2015
2014
Thermal-hydr Dsgn Nuc Rc (3c)
  • Michael Podowski
Seats Taken: 9/30
2013
2012
Thermal-hydr Dsgn Nuc Rc (3c)
  • Michael Podowski
Seats Taken: 8/15
2011
2010
2009
2008
2007