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

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Abstracts and Available Papers Presented at the
2002 International RERTR Meeting


K. Bakker, F. Wijtsma

NRG-Petten, P.O. Box 25, 1755 ZG  Petten, The Netherlands.

A. Bos, C. Mol, H. Rakhorst,

Urenco Nederland B.V., P.O. Box 158, 7600 AD  Almelo, The Netherlands.

M. Bretscher, G. Hofman, J. Snelgrove

Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Il 60439-4815.


In recent years significant interest was gained in UMo fuel to be used in Material Test Reactors. This interest was induced by the fact that UMo fuel is mechanically stable, even at high uranium concentrations and high U-burnup. These properties are required in order to use Low Enriched Uranium (LEU) and still be able to achieve high flux and burnup values and, thus, to facilitate the conversion from High Enriched Uranium (HEU) to LEU.

Neutronics computations have shown that, although the Mo concentration in UMo fuel is not very high (about 5 - 10w%), the neutron absorption cross sections of natural Mo are sufficiently high to have a considerable negative impact on the reactivity of this UMo fuel. In the present research the neutron absorption cross sections of natural Mo are discussed and the option to reduce the cross section of molybdenum by depleting the Mo in 95Mo is described. Finally the economic consequences of using Mo depleted in 95Mo are briefly discussed.

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Mr. Fred Jan Wijtsma

Reactor Manager HFR&LFR
Nuclear Research and Consultancy Group
P.O. Box 25, 1755 ZG Petten
The Netherlands
Phone: (31 224) 56 58 13
Fax: (31 224) 56 59 99
E-mail: [email protected]

2016 RERTR Meeting

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2015 RERTR Meeting

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For more information visit RERTR-2015.


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