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

Home  :: 1999 International RERTR Meeting Program  :: Related Documents

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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Last modified on July 29, 2008 11:33 +0200