Theses most similar to those of author O'Brien, Lindsay Beth

The effect of environment, chemistry, and microstructure on the corrosion fatigue behavior of austenitic stainless steels in high temperature water (2014) 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
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Thermal-mechanical fatigue behavior of nickel-base superalloys

Marchand, Norman J (1986)

  • Advisor: R.M. Pelloux
  • Department of Materials Science and Engineering
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Hydrogen degradation and microstructural effects of the near-threshold fatigue resistance of pressure vessel steels

Fuquen-Molano, Rosendo (1982)

  • Advisor: Robert O. Ritchie
  • Department of Materials Science and Engineering
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Effect of strength, load ratio and environment on near-threshold fatigue crack propagation of 2 1/4 Cr - 1 Mo steel

Zamiski, Gerald Frank (1980)

  • Advisor: Robert O. Ritchie
  • Department of Mechanical 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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Time dependent crack growth in quartz and its application to the creep of rocks,

Martin, Randolph J. (Randolph James) (1971)

  • Advisor: William F. Brace
  • Department of Earth, Atmospheric, and Planetary Sciences
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Behavior of alloy 617 at 650°C in low oxygen pressure environments

Mas, Fanny (Fanny P.) (2010)

  • Advisor: Ballinger, Ronald George
  • Department of Materials Science and Engineering
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Materials testing and development of functionally graded composite fuel cladding and piping for the Lead-Bismuth cooled nuclear reactor

Fray, Elliott Shepard (2013)

  • Advisor: Ballinger, Ronald George
  • Department of Nuclear Science and 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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