Abstracts and Available Papers Presented at the
2004 International RERTR Meeting
FLUX ENHANCEMENT OPTIONS FOR AN LEU-FUELED MIT REACTOR
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
ABSTRACT
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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Contact:
Dr. Jordi Roglans-Ribas
Technical Director, RERTR Department
Nuclear Engineering Division – 362
Argonne National Laboratory
9700 South Cass Avenue
Argonne, IL 60439
Fax: +1 630-252-5161
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