Abstracts and Available Papers Presented at the
1999 International RERTR Meeting
NEUTRONIC SAFETY PARAMETERS AND TRANSIENT ANALYSES FOR POTENTIAL LEU CONVERSION OF THE BUDAPEST RESEARCH REACTOR
R. B. Pond, N. A.
Hanan and J. E. Matos
Argonne National
Laboratory
Argonne, IL, USA
And
Csaba Maráczy
KFKI Atomic Energy
Research Institute
Budapest, Hungary
ABSTRACT
An initial safety study for potential LEU conversion of the Budapest Research Reactor was completed. The study compares safety parameters and example transients for reactor cores with HEU and LEU fuels. Reactivity coefficients, kinetic parameters and control rod worths were calculated for cores with HEU (36%) UAl alloy fuel and UO2-Al dispersion fuel, and with LEU (19.75%) UO2-Al dispersion fuel that has a uranium density of about 2.5 g/cm3. A preliminary fuel conversion plan was developed for transition cores that would convert the BRR from HEU to LEU fuel in 3-4 years after the process is begun.
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Contact:
Raymond B. Pond
Physicist
Technology
Development - 362
Argonne National
Laboratory
9700 South Cass
Avenue
Argonne, IL 60439
USA
Phone: (630) 252-7090
Fax: (630) 252-5161
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