This report contains the results of reactor design and performance calculations for conversion of the Massachusetts Institute of Technology Reactor (MITR) from the use of highly-enriched uranium (HEU) fuel to the use of low-enriched uranium (LEU) fuel. The analyses were performed by staff members of the Global Threat Reduction Initiative (GTRI) Reactor Conversion Program at the Argonne National Laboratory (ANL) and the MITR Facility. The core conversion to LEU is being performed with financial support from the U. S. government.In the framework of its non-proliferation policies, the international community presently aims to minimize the amount of nuclear material available that could be used for nuclear weapons. In this geopolitical context most research and test reactors, both domestic and international, have started a program of conversion to the use of LEU fuel. A new type of LEU fuel based on an alloy of uranium and molybdenum (U-Mo) is expected to allow the conversion of U.S. domestic high performance reactors like MITR. This report presents the nominal steady-state irradiation conditions of plates containing peak irradiation parameters found in MITR cores fueled with the LEU monolithic U-Mo alloy fuel with 10 wt% Mo. Manufacturing tolerances and other uncertainties in reactor geometry and materials are also presented and used to estimate the uncertainties in these irradiation parameters above nominal steadystate conditions.
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