Home / Publications / Journals / Nuclear Technology / Volume 126 / Number 1
Nuclear Technology / Volume 126 / Number 1 / April 1999 / Pages 88-101
Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT99-A2960
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Models for the interaction of uranium silicide dispersion fuels with an aluminum matrix, for the resultant reaction product swelling, and for the calculation of the stress gradient within the fuel particles are described within the context of DART fission-gas-induced swelling models. The effects of an aluminide shell on fuel particle swelling are evaluated. Validation of the model is demonstrated by comparing DART calculations with irradiation data for the swelling of U3SiAl-Al and U3Si2-Al in variously designed dispersion fuel elements.