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

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Abstracts and Available Papers Presented at the
2002 International RERTR Meeting


M. M. Bretscher, N. A. Hanan, and J. E. Matos
RERTR Program
Technology Development Division
Argonne National Laboratory
Argonne, Illinois 60439-4815 USA


B. S. Yuldashev, S. Baytelesov, and A. Rakhmanov
Institute of Nuclear Physics
Tashkent, Uzbekistan



The 10 MW WWR-SM research reactor in Uzbekistan currently uses HEU (36%) IRT-3M 6-tube fuel assemblies manufactured by the Novosibirsk Chemical Concentrates Plant in Russia.  Recent 4x4 core configurations reflected by beryllium have been operated at 8 MW.  The Institute of Nuclear Physics plans to convert the reactor to LEU (19.7%) fuel as soon as a suitable LEU fuel assembly is qualified.  This study compares the neutronic performance of the reactor and its experiments using LEU pin-type and LEU tube-type fuel assembly designs with the current HEU (36%) reference fuel assembly.

Both 3D Monte Carlo and 3D diffusion theory calculations were performed to analyze a critical core configuration with partially-burned HEU fuel assemblies in order to establish the credibility of the analytical methods and computer models used to describe the reactor and its experiments.  Results based on these techniques are in reasonable agreement with the measured data.

An LEU pin-type design (164 pins, 4.5 g U/cm3, 375g 235U) or an LEU tube-type design (IRT-3M, 6-tube, 5.4 gU/cm3, and 364g 235U) with U9Mo-Al fuel meat could operate with about the same cycle length and experiment load as the reference HEU (36%) IRT-3M fuel.  The annual fuel assembly consumption would be nearly the same in these HEU and LEU cores.  For the LEU pin-type design, fast (thermal) fluxes would be reduced by 2.5% (14%) for experiments located at the center of the fuel assemblies and by 0.5% (4%) for experiments located in experiment channels in the beryllium reflector.  For the LEU tube-type design, fast (thermal) fluxes would be reduced by 3.5% (15%) for experiments located at the center of the fuel assemblies and by 1.2% (5%) for experiments located in experiment channels in the beryllium reflector.

If the 235U content of the LEU pin-type fuel assemblies were increased to 480g (using pins similar to those planned to be tested in the WWR-M reactor at Gatchina, Russia in 2003 and 2004), the annual consumption of fuel assemblies would be reduced by about 35%.  Fast (thermal) fluxes would decrease by about 3.5% (27%) in the experiment positions in the core and by about 1.5% (8%) in the experiment positions in the beryllium reflector.  However, for this 4x4 core configuration the LEU IRT-4M 6-tube fuel assemblies with UO2-Al fuel meat, ~3 gU/cm3, and 265g 235U would increase the annual fuel assembly consumption by over 300%. 

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Dr. Nelson Hanan
Nuclear Engineer
Argonne National Laboratory
9700 South Cass Avenue
Argonne, IL 60439 USA

Phone: (630) 252-6627
Fax:     (630) 252-5161

2016 RERTR Meeting

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2015 RERTR Meeting

The 2015 International RERTR Meeting (RERTR-2015) took place in Seoul, Korea on Oct. 11-14, 2015.
For more information visit RERTR-2015.


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Last modified on July 29, 2008 11:34 +0200