Abstracts and Available Papers Presented at the Meeting
Core Design
and Analysis for the MIT Reactor Using Monolithic U-Mo
LEU Fuel
Thomas H. Newton, Jr.
Nuclear Reactor Laboratory
Massachusetts Institute of Technology
Cambridge, MA 02139
ABSTRACT
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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2006 International RERTR Meeting
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