Home / Publications / Journals / Nuclear Technology / Volume 42 / Number 3
Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 332-334
Technical Paper / Material / dx.doi.org/10.13182/NT79-A32188
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Previous authors have proposed that temperature gradient effects could produce significant contributions to cladding dilatation in a fast reactor fuel pin during irradiation. An expression for their suggested mechanisms of thermomigration and diffusion has been derived in irradiation-induced concentration gradients. Evaluation shows that the cladding dilatation is negligible, but less direct effects of the temperature gradient could be important.