Nuclear Reactor Material

MANE-6380

The physical metallurgy and associated physical chemistry of problems encountered in the application of materials in nuclear reactors is discussed. Specifically, the metallurgy and physical chemistry of ceramic fuels (e.g., oxygen potentials), the primary fuel densification and pellet-clad interaction mechanisms, irradiation-induced creep, hardening, and embrittlement mechanisms, and the properties of zircaloy are covered.

3 credits

Past Term Data

Offered
Not Offered
Offered as Cross-Listing Only
No Term Data
Spring Summer Fall
(Session 1) (Session 2)
2025
Nuclear Reactor Material (3c)
  • Jie Lian
Seats Taken: 0/30
2024
Nuclear Reactor Material (3c)
  • Jie Lian
Seats Taken: 2/30
2023
2022
Nuclear Reactor Material (3c)
  • Jie Lian
Seats Taken: 6/10
2021
Nuclear Reactor Material (3c)
  • Jie Lian
Seats Taken: 12/20
2020
Nuclear Reactor Material (3c)
  • Jie Lian
Seats Taken: 7/8
2019
2018
Nuclear Reactor Material (3c)
  • Jie Lian
Seats Taken: 5/15
2017
Nuclear Reactor Material (3c)
  • Jie Lian
Seats Taken: 12/15
2016
2015
Nuclear Reactor Material (3c)
  • Jie Lian
Seats Taken: 6/15
2014
Nuclear Reactor Material (3c)
  • Jie Lian
Seats Taken: 10/15
2013
Nuclear Reactor Material (3c)
  • Jie Lian
Seats Taken: 8/15
2012
2011
Nuclear Reactor Material (3c)
  • Jie Lian
Seats Taken: 1/15
2010
Nuclear Reactor Material (3c)
  • Jie Lian
Seats Taken: 5/15
2009
Nuclear Reactor Material (3c)
  • Jie Lian
Seats Taken: 8/15
2008
Nuclear Reactor Material (3c)
  • Hanchen Huang
Seats Taken: 12/15
2007
2006
2005
2004
2003
2002
2001
2000
1999
1998