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
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.
Full paper in PDF format
- Core Design and
Analysis for the MIT Reactor Using Monolithic U-Mo LEU
Fuel, T. H. Newton
[PDF, 261KB, 10 pages]
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Dr. Jordi Roglans-Ribas
Technical Director, RERTR Department
Nuclear Engineering Division – 362
Argonne National Laboratory
9700 South Cass Avenue
Argonne, IL 60439
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