Theses most similar to Stress corrosion cracking and crack tip characterization of Alloy X-750 in light water reactor environments (Gibbs, Jonathan Paul; 2011) read it

Corrosion fatigue crack initiation in 2091-T351 Alclad

Genkin, Jean-Marc P. (Jean-Marc Patrick) (1996)

  • Advisor: Ballinger, Ronald George
  • Department of Materials Science and Engineering
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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
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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
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Corrosion of various engineering alloys in supercritical carbon dioxide

Gibbs, Jonathan Paul (2010)

  • Advisors: Ballinger, Ronald George; Thomas McKrell
  • Department of Materials Science and Engineering
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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
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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
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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
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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
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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
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Safety of light water reactor fuel with silicon carbide cladding

Lee, Youho (2013)

  • Advisor: Mujid S. Kazimi
  • Department of Nuclear Science and Engineering
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