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Marino, G.P.; Fischer, R.L.
Bettis Atomic Power Lab., West Mifflin, PA (USA)1978
Bettis Atomic Power Lab., West Mifflin, PA (USA)1978
AbstractAbstract
[en] Seamless Zircaloy-4 tubing is utilized as fuel rod cladding in light water reactors. Water corrosion tests at 68OF have been performed to determine the corrosion and hydriding characteristics of Zircaloy-4 tubing, fabricated by cold reduction and finished in two metallurgical conditions: a stress-relief anneal (SRA) and a recrystallization anneal (RXA). These corrosion tests revealed differences in the post-transition corrosion product weight gains of the two materials. A computer corrosion model, designated CHORT, was developed from the test data and ascribes the observed difference in material weight gain to an assumed difference in the periodicity of a postulated cyclic buckling of the oxide
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Dec 1978; 29 p; Available from NTIS., PC A03/MF A01
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