Argonne National Laboratory
Reduced Enrichment for Research and Test Reactors
Nuclear Engineering Division at Argonne
U.S. Department of Energy

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Abstracts and Available Papers Presented at the
2004 International RERTR Meeting


Thomas H. Newton, Jr., Edward E. Pilat, and Mujid S. Kazimi
Nuclear Reactor Laboratory and Nuclear Engineering Department
Massachusetts Institute of Technology 138 Albany St. Cambridge, MA 02139


The Monte-Carlo transport code MCNP was used to evaluate possible arrangements of cores for the MIT Reactor using monolithic LEU fuel. Plate and moderator thicknesses were varied, and fixed absorbers and inner reflectors added in an effort to maximize available neutron fluxes at in-core and ex-core locations of experimental facilities. Addition of D2O in the H2O moderator was also evaluated. Comparisons of the fast, epithermal, and thermal fluxes were made at selected locations. Keff was also evaluated and critical blade heights compared with the existing HEU core. Results indicate that the LEU fluxes could approach HEU values with the use of a fueled in-core experimental facility, a fixed boron absorber spider and an inner beryllium reflector.

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

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2015 RERTR Meeting

The 2015 International RERTR Meeting (RERTR-2015) took place in Seoul, Korea on Oct. 11-14, 2015.
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Last modified on July 29, 2008 11:33 +0200