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Design and feasibility studies for conversion of the MIT Reactor have shown that the current HEU experimental performance will be maintained with the use of monolithic U-10Mo LEU fuel and an upgrade in operating power from 6 MW to 7 MW. Power peaking for a number of LEU core configurations has been analyzed using the MCNP-ORIGEN coupling code MCODE. This power peaking has been used in steady-state thermal-hydraulic analysis with the result that the limiting safety system setting power based on the onset of nucleate boiling is 7.7 MW.Because total fuel lifetime may be limited by cladding oxide growth,quantification of the distribution of oxide on the finned aluminum cladding of the MITR HEU fuel elements have been made using a replication process and eddy current measurements. Results of these measurements will be presented.