Theses most similar to Application and economic feasibility of functionally graded composite for lead-bismuth service (Handra; 2008) read it
Design, analysis and optimization of the power conversion system for the Modular Pebble Bed Reactor System
Wang, Chunyun, 1968- (2003)
- Advisor: Ballinger, Ronald George
- Department of Nuclear Engineering
- Advisor: Todreas, Neil Emmanuel
- 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
Modeling and design of reload LWR cores for an ultra-long operating cycle
McMahon, Michael Vincent (1998)
- Advisors: Michael J. Driscoll; Todreas, Neil Emmanuel
- Department of Nuclear Engineering
Thermal hydraulic design and analysis of a large lead-cooled reactor with flexible conversion ratio
Nikiforova, Anna S. (2008)
- Advisors: Hejzlar, Pavel; Todreas, Neil Emmanuel
- Department of Nuclear Science and Engineering
Economics of nuclear fuel cycles : option valuation and neutronics simulation of mixed oxide fuels
De Roo, Guillaume (2009)
- Advisors: Benoit Forget; John E. Parsons
- Department of Nuclear Science and Engineering; Engineering Systems Division; Technology and Policy Program
Impact of alternative nuclear fuel cycle options on infrastructure and fuel requirements, actinide and waste inventories, and economics
Guérin, Lauren (2009)
- Advisor: Mujid S. Kazimi
- Department of Aeronautics and Astronautics; Engineering Systems Division; Technology and Policy Program
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
Examination of the conversion of the U.S. submarine fleet from highly enriched uranium to low enriched uranium
McCord, Cameron (Cameron Liam) (2014)
- Advisor: R. Scott Kemp
- Department of Nuclear Science and Engineering
Design optimization and analysis of a fluoride salt cooled high temperature test reactor for accelerated fuels and materials testing and nonproliferation and safeguards evaluations
Richard, Joshua (Joshua Glenn) (2016)
- Advisor: Benoit Forget
- Department of Nuclear Science and Engineering