Theses most similar to those of author Ensor, Brendan M. (Brendan Melvin)
Thermal analysis of uranium zirconium hydride fuel using a lead-bismuth gap at LWR operating temperatures (2012) 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
- Advisor: Hejzlar, Pavel
- Department of Nuclear Engineering
Performance analysis of matrix fuel for a passive pressure tube light water reactor
Mattingly, Brett T. (Brett Thomas) (1995)
- Advisor: Todreas, Neil Emmanuel
- Department of Nuclear Engineering
- Advisor: Mujid S. Kazimi
- 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
Design and optimization of a high thermal flux research reactor via Kriging-based algorithm
Kempf, Stephanie Anne (2011)
- Advisors: Ben Forget; Lin-wen Hu
- Department of Nuclear Science and Engineering
Reactor physics considerations for implementing silicon carbide cladding into a PWR environment
Dobisesky, Jacob P. (Jacob Paul), 1987- (2011)
- Advisor: Mujid S. Kazimi
- Department of Nuclear Science and Engineering
Tritium production analysis and management strategies for a Fluoride-salt-cooled high-temperature test reactor (FHTR)
Rodriguez, Judy N (2013)
- Advisor: Lin-Wen Hu
- Department of Nuclear Science and Engineering
Preventing fuel failure for a beyond design basis accident in a fluoride salt cooled high temperature reactor
Minck, Matthew J. (Matthew Joseph) (2013)
- Advisor: Charles Forsberg
- Department of Nuclear Science and Engineering
Evaluation of multilayer silicon carbide composite cladding under loss of coolant accident conditions
Daines, Gregory Welch (2016)
- Advisor: Michael P. Short
- Department of Nuclear Science and Engineering