Abstracts and Available Papers Presented at the Meeting
and Analysis for the MIT Reactor Using Monolithic U-Mo
Thomas H. Newton, Jr.
Nuclear Reactor Laboratory
Massachusetts Institute of Technology
Cambridge, MA 02139
Initial studies have been performed
using MCNP to determine the feasibility of using
monolithic U-Mo LEU fuel in the MIT Reactor. A
preliminary design was chosen so that the fluxes at
in-core and ex-core experimental facilities were made
equivalent to those using the current HEU aluminide
fuel. Safety analyses of the LEU design showed an
increase in thermal-hydraulic safety margins and
allowable step reactivity.
Design studies for further evaluation of proposed LEU
cores using burned fuel are proceeding using the MCNP/ORIGEN2
coupling code MCODE and the diffusion theory code REBUS
using a triangular-Z matrix.
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