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, IL, USA
KFKI Atomic Energy
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.