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Reduced Enrichment for Research and Test Reactors
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U.S. Department of Energy

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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

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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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