Method for determining corrosion susceptibility of nuclear fuel

Induced nuclear reactions: processes – systems – and elements – Handling of fission reactor component structure within...

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376277, 376305, 436 6, 436908, G21C 1900

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059913525

ABSTRACT:
A method for determining the susceptibility of a sample of Zircaloy alloy to nodular corrosion. A specimen of such Zircaloy sample is annealed at a temperature within a temperature range bounded at its upper limit by the temperature T.sub.c being the temperature at equilibrium wherein sufficient solute would exist in the (.alpha.-matrix of the particular zircaloy to resist nodular corrosion, and bounded by a lower temperature, such temperature being the temperature of the (.alpha.+precipitate)/(.alpha.+.beta.+precipitate) transus for the particular Zircaloy sample. For Zircaloy-2, such temperature range is from approximately 825.degree. C. to 841.degree. C. The specimen is maintained at such selected temperature within such temperature range for a measured period, and subsequently exposed to steam at a fixed temperature and pressure for a fixed time. If nodular corrosion does not appear the above steps are repeated, but on each different specimen increasing the measured time period until a last measured time period is obtained when nodular corrosion first appears on a specimen. The length of the last measured time period is used as an indicator of the sample's resistance to nodular corrosion, and thus conversely its susceptibility to nodular corrosion.

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"Zirconium in the Nuclear Industry", by Ronald B. Adamson et al., ASTM Special Technical Publication 939, Seventh International Symposium sponsor by ASTM Committee B-10 on Reactive and Refractory Metals, Strasbourg, France, Jun. 24-27, 1985, pp. 419 and 423.

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