Abstracts and Available Papers Presented at the
1998 International RERTR Meeting
A Neutronic Feasibility Study for LEU Conversion of the IR-8 Research Reactor
J. R. Deen, N. A. Hanan and J. E. Matos
Argonne National Laboratory
Argonne, IL, USA
and
P. Egorenkov and V. A. Nasonov
Russian Research Center 'Kurchatov Institute'
Moscow, Russia
Abstract
Equilibrium fuel cycle comparisons were made for HEU and LEU fuel
options using three-dimensional multi-group diffusion theory models benchmarked to exact
Monte Carlo models of the IR-8 core. Comparisons were made of changes in reactivity, cycle
length, fuel burnup, thermal neutron flux for the 90% and 36% enriched IRT-3M fuel
assembly and the 19.75% enriched IRT-4M fuel assembly with the same fuel management
strategy. The results of these comparisons showed that a 3.48gU/cc fuel meat density would
be required in the LEU IRT-4M fuel assembly to provide core reactivity equivalent to the
reference HEU fuel cycle.
PDF version available
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Contact:
James R. Deen
Argonne National Laboratory
9700 S.Cass Avenue, Bldg 207
Argonne IL 60439
USA
Phone: 1 630 252 4853
Fax: 1 630 252 5161
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