Home / Publications / Journals / Nuclear Technology / Volume 93 / Number 2
Nuclear Technology / Volume 93 / Number 2 / February 1991 / Pages 221-239
Technical Paper / Material/Nuclear Safety / dx.doi.org/10.13182/NT91-A34507
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Zircaloy oxidation and hydrogen generation data from several in-pile severe fuel damage experiments are presented and compared. Common findings indicate that the extent of bundle oxidation is largely controlled by steam supply conditions, that high rates of hydrogen generation continued after melt formation and relocation, and that total flow area blockages necessary for termination of oxidation did not develop. Test results indicate no apparent limitations to Zircaloy oxidation other than those due to steam supply and known reaction kinetics.