Theses most similar to Integrated environmental degradation model for Fe-Ni-Cr alloys in irradiated aqueous solutions (Pleune, Thomas Todd, 1974-; 1999) read it
Design, construction, and commissioning of an in-core materials testing facility for slow strain rate testing
O'Donnell, Jeffrey R. (Jeffrey Robert) (1994)
- Advisor: Otto K. Harling
- Department of Nuclear Engineering
- Advisor: Mujid Kazimi
- 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
- Advisor: Mujid S. Kazimi
- 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
The effect of thermal aging and boiling water reactor environment on Type 316L stainless steel welds
Lucas, Timothy R (2011)
- Advisor: Ballinger, Ronald George
- Department of Nuclear Science and Engineering
Behavior of triplex silicon carbide fuel cladding designs tested under simulated PWR conditions
Stempien, John D. (John Dennis) (2011)
- Advisor: Mujid S. Kazimi
- 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
- Advisor: Ballinger, Ronald George
- Department of Nuclear Science and Engineering