Home / Publications / Journals / Nuclear Technology / Volume 16 / Number 1
Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 89-99
Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31178
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Experimental determinations of cladding plastic deformation in (U,Pu)O2 fuel rods, clad with annealed Type 316 stainless steel and irradiated in EBR-II, indicate that fuel-cladding mechanical interaction takes place between ∼3 and 8 at.% burnup. At higher burnups, the cladding swelling rate increases markedly resulting in no further fuel-induced plastic deformation. The maximum cladding plastic strain exhibited by several annealed Type 316 stainless-steel-clad rods was 0.4%. Cladding plastic strain was found to be independent of smeared density in the range of 83 to 91% TD.