Theses most similar to Thermal hydraulics analysis of the MIT research reactor in support of a low enrichment uranium (LEU) core conversion (Ko, Yu-Chi; 2008) read it
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- Department of Nuclear Engineering
Advanced design concepts for PWR and BWR high-performance annular fuel assemblies
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Thermal hydraulic design of a 2400 MW t̳h̳ direct supercritical CO₂-cooled fast reactor
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Lee, Jeongik (2007)
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- Department of Nuclear Science and Engineering
- Advisor: Mujid S. Kazimi
- Department of Nuclear Science and Engineering
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Loss-of-flow analysis of an unfinned, graded fuel meat, LEU monolithic U-10Mo fuel design in support of the MITR-II fuel conversion
Don, Sarah M (2014)
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