Theses most similar to those of author Stempien, John D. (John Dennis)
Behavior of triplex silicon carbide fuel cladding designs tested under simulated PWR conditions (2011) read it
- Advisor: S. Mark Spearing
- Department of Aeronautics and Astronautics
Hybrid silicon/silicon carbide microstructures and silicon bond strength tests for the MIT Microengine
Miller, Bruno, 1974- (2000)
- Advisor: S. Mark Spearing
- Department of Aeronautics and Astronautics
An Exploration of the Effect of Temperature on Different Alloys in a Supercritical Carbon Dioxide Environment
Dunlevy, Michael William (2009)
- Advisor: Ballinger, Ronald George
- 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
- Advisor: Mujid S. Kazimi
- Department of Nuclear Science and Engineering
An improved structural mechanics model for the FRAPCON nuclear fuel performance code
Mieloszyk, Alexander James (2012)
- 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
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
Design optimization of advanced PWR SiC/SiC fuel cladding for enhanced tolerance of loss of coolant conditions
Guenoun, Pierr (2016)
- Advisor: Michael Short
- Department of Nuclear Science and Engineering
Tritium transport, corrosion, and Fuel performance modeling in the Fluoride Salt-Cooled High-Temperature Reactor (FHR) (2015) read it
Conceptual design of a lead-bismuth cooled fast reactor with in-vessel direct-contact steam generation
Buongiorno, Jacopo, 1971- (2001)
- Advisors: Kenneth R. Czerwinski; Todreas, Neil Emmanuel
- Department of Nuclear Engineering
Design optimization and analysis of coated particle fuel using advanced fuel performance modeling techniques
Soontrapa, Chaiyod (2005)
- Advisor: Ballinger, Ronald George
- Department of Nuclear Engineering
- Advisor: Michael W. Golay William W. Hoga
- Department of Nuclear Engineering
Thermal hydraulic design of a 2400 MW t̳h̳ direct supercritical CO₂-cooled fast reactor
Pope, Michael A. (Michael Alexander) (2006)
- Advisor: Michael J. Driscoll
- Department of Nuclear Science and Engineering
Implementation of vented fuel assemblies in the supercritical CO₂-cooled fast reactor
McKee, Stephanie A (2008)
- Advisor: Michael J. Driscoll
- Department of Nuclear Science and Engineering
- Advisor: Mujid S. Kazimi
- Department of Nuclear Science and Engineering
Application and economic feasibility of functionally graded composite for lead-bismuth service
Handra (2008)
- Advisor: Ballinger, Ronald George
- Department of Materials Science and Engineering
General analysis of breed-and-burn reactors and limited-separations fuel cycles
Petroski, Robert C (2010)
- Advisor: Benoit Forget
- Department of Nuclear Science and Engineering
Silicon carbide performance as cladding for advanced uranium and thorium fuels for light water reactors
Sukjai, Yanin (2014)
- Advisor: Mujid S. Kazimi
- Department of Nuclear Science and Engineering
Application of advanced fuel concepts for use in innovative pressurized water reactors
Andrews, Nathan Christopher (2015)
- Advisor: Mujid S. Kazimi
- Department of Nuclear Science and Engineering