Theses most similar to The effect of thermal aging and boiling water reactor environment on Type 316L stainless steel welds (Lucas, Timothy R; 2011) read it
- Advisor: Ballinger, Ronald George
- Department of Nuclear Engineering
Irradiation assisted stress corrosion cracking susceptibility of low fluence stainless steels evaluated by in-flux slow strain rate tests
Hilton, Bruce A (1996)
- Advisors: Gordon E. Kohse; Otto K. Harling
- Department of Nuclear Engineering
Evaluation of radiation induced segregation in Fe-Ni-Cr alloys
Flores, Carlos D. (Carlos Daniel) (1994)
- Advisor: Ballinger, Ronald George
- Department of Materials Science and Engineering; Department of Nuclear Engineering
Relationship of grain boundary structure and mechanical properties of Inconel 690
Marra, Joseph J (2009)
- Advisor: Yildiz, Bilge, 1976-
- Department of Mechanical Engineering; Department of Nuclear Science and Engineering
Stress corrosion cracking and crack tip characterization of Alloy X-750 in light water reactor environments
Gibbs, Jonathan Paul (2011)
- Advisors: Ballinger, Ronald George; John H. Jackson
- Department of Nuclear Science and Engineering
- Advisor: Ballinger, Ronald George
- Department of Nuclear Science and Engineering
An assessment of silicon carbide as a cladding material for light water reactors
Carpenter, David Michael (2010)
- Advisor: Mujid S. Kazimi
- Department of Nuclear Science and Engineering
Effect of residual stress on the life prediction of dry storage canisters for used nuclear fuel
Black, Bradley P. (Bradley Patrick) (2013)
- Advisor: Ballinger, Ronald George
- Department of Nuclear Science and Engineering
Integrated environmental degradation model for Fe-Ni-Cr alloys in irradiated aqueous solutions
Pleune, Thomas Todd, 1974- (1999)
- Advisor: Ballinger, Ronald George
- Department of Nuclear Engineering
Fatigue crack growth of Incoloy 908 at high temperature
Hughes, Rachelle J. (Rachelle Jane), 1974- (1999)
- Advisors: Ballinger, Ronald George; Kenneth C. Russell
- Department of Materials Science and Engineering; Department of Nuclear Engineering