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Reduced Enrichment for Research and Test Reactors
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Abstracts and Available Papers Presented at the
2004 International RERTR Meeting

Analyses for Inserting Fresh LEU Fuel Assemblies Instead of Fresh HEU Fuel Assemblies in the Dalat Nuclear Research Reactor in Vietnam

N.A. Hanan, J.R. Deen, and J.E. Matos
RERTR Program Argonne National Laboratory Argonne, Illinios 60439, USA
 


ABSTRACT
 

Analyses were performed by the RERTR Program to replace 36 burned HEU (36%) fuel assemblies in the Dalat Nuclear Research Reactor in Vietnam with either 36 fresh fuel assemblies currently on-hand at the reactor or with LEU fuel assemblies to be procured. The study concludes that the current HEU (36%) WWR-M2 fuel assemblies can be replaced with LEU WWR-M2 fuel assemblies that are fully-qualified and have been commercially available since 2001 from the Novosibirsk Chemical Concentrates Plant in Russia.

The current reactor configuration using re-shuffled HEU fuel began in June 2004 and is expected to allow normal operation until around August 2006. If 36 HEU assemblies each with 40.2 g 235U are inserted without fuel shuffling over the next five operating cycles, the core could operate for an additional 10 years until June 2016. Alternatively, inserting 36 LEU fuel assemblies each containing 49.7 g 235U without fuel shuffling over five operating cycles would allow normal operation for about 14 years from August 2006 until October 2020. The main reason for the longer service life of the LEU fuel is that its 235U content is higher than the 235U content needed simply to match the service life of the HEU fuel. Fast neutron fluxes in the experiment regions would be very nearly the same in both the HEU and LEU cores. Thermal neutron fluxes in the experiment regions would be lower by 1-5%, depending on the experiment type and location.


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