journal article·2009-01

Growth of the interaction layer around fuel particles in dispersion fuel

D. Olander

Journal of Nuclear Materials· Volume 383· Issue 3
Publisher page

Abstract

Abstract Corrosion of uranium particles in dispersion fuel by the aluminum matrix produces interaction layers (an intermetallic-compound corrosion product) around the shrinking fuel spheres. The rate of this process was modeled as series resistances due to Al diffusion through the interaction layer and reaction of aluminum with uranium in the fuel particle to produce UAlx. The overall kinetics are governed by the relative rates of these two steps, the slowest of which is reaction at the interface between Al in the interaction layer and U in the fuel particle. The substantial volume change as uranium is transferred from the fuel to the interaction layer was accounted for. The model was compared to literature data on in-reactor growth of the interaction layer and the Al/U gradient in this layer, the latter measured in ex-reactor experiments. The rate constant of the Al–U interface reaction and the diffusivity of Al in the interaction layer were obtained from this fitting procedure. The second feature of the corrosion process is the transfer of fission products from the fuel particle to the interaction layer due to the reaction. It is commonly assumed that the observed swelling of irradiated fuel elements of this type is due to release of fission gas in the interaction layer to form large bubbles. This hypothesis was tested by using the model to compute the quantity of fission gas available from this source and comparing the pressure of the resulting gas with the observed swelling of fuel plates. It was determined that the gas pressure so generated is too small to account for the observed delamination of the fuel.
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Research context

OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Radioactive element chemistry and processing

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References (8)

Show source-provided references
1. Ryu · J. Nucl. Mater. · 2002 · 321 · 21010.1016/S0022-3115(03)00251-4 ↗
2. Leenaers · J. Nucl. Mater. · 2004 · 335 · 3910.1016/j.jnucmat.2004.07.004 ↗
3. S. Van den Berghe et al., Transmission electron microscopy of irradiated U, Mo dispersion fuel, RERTR-2007 International Meeting on Reduced Enrichment for Research and Test Reactors, Prague, Czech Republic, September 2007.
4. Soba · J. Nucl. Mater. · 2007 · 360 · 23110.1016/j.jnucmat.2006.09.014 ↗
5. Y.S. Kim, Personal communication.
6. H. Mehrer, Presented at the International Max Planck Research School for Advanced Studies, Stuttgart Germany, 2006, .
7. Matzke · J. Less-Common Metals · 1986 · 121 · 53710.1016/0022-5088(86)90573-4 ↗
8. Über einige Probleme der Theorie der Wärmeleitung