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2006 International RERTR Meeting

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.

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Dr. Jordi Roglans-Ribas
Technical Director, RERTR Department
Nuclear Engineering Division 362
Argonne National Laboratory
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Argonne, IL 60439
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2016 RERTR Meeting

The 2016 International RERTR Meeting (RERTR-2016) will take place in Belgium. Stay tuned for further details.

2015 RERTR Meeting

The 2015 International RERTR Meeting (RERTR-2015) took place in Seoul, Korea on Oct. 11-14, 2015.
For more information visit RERTR-2015.


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Last modified on July 29, 2008 15:16 +0200