Abstracts and Available Papers Presented at the 2003 International RERTR Meeting
Preliminary
INVESTIGATION of the Use of Monolithic U-Mo Fuel in the
MIT Reactor
Thomas H. Newton, Jr.
Nuclear Reactor
Laboratory
Massachusetts
Institute of Technology
138 Albany St.
Cambridge, MA 02139
and
Mujid S. Kazimi,
Edward E. Pilat and Zhiwen Xu
Nuclear Engineering
Department
Massachusetts
Institute of Technology
Cambridge, MA 02139
ABSTRACT
Studies have begun on the use
of monolithic LEU U-Mo fuel in the MIT Nuclear Research Reactor (MITR-II) using
the Monte Carlo Transport code MCNP.
These studies have included model benchmarking, LEU fuel optimization,
burnup evaluation, in-core facility design, and determination of safety
attributes. Benchmarking studies on the
initial core have shown favorable agreement between the calculated and measured
reactivity worths of the six control blades.
In addition, optimization studies on LEU U7Mo MITR-II fuel have shown
that an arrangement of ten to twelve plates per fuel element would have initial
reactivity values and thermal neutron fluxes comparable to the current HEU
core. Burnup studies which have been made using the MCODE depletion program
will be presented. Safety attributes
such as temperature coefficients, shutdown margins, and coolant subcooled
margin are under evaluation.
Contact: Mr. Thomas Newton
Reactor
Engineer
Massachusetts
Institute of Technology
138 Albany
St.
Cambridge, MA
02139 USA
Phone: +1 (617) 253-4211
Fax: +1 (617) 253-7300
E-mail: [email protected]
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