Browsing Undergraduate Theses by Subject "Nuclear fuel elements Computer programs"
Now showing items 1-4 of 4
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Comparison of conservative and best estimate heat transfer packages with COBRA-IV-I.
(Massachusetts Institute of Technology, 1978) -
MITR-II fuel management, core depletion, and analysis : codes developed for the diffusion theory program CITATION
(Massachusetts Institute of Technology, 1979) -
Reactor thermal-hydraulic analysis improvement and application of the code COBRA-IIIC/MIT
(Massachusetts Institute of Technology, 1981) -
Sensitivity study of the assembly averaged thermal-hydraulic models of the MEKIN computer code in power transients
(Massachusetts Institute of Technology, 1977)