Mechanical behavior at high temperature of highly oxygen- or hydrogen-enriched α and (prior-) $\beta$ phases of zirconium alloys - CEA - Commissariat à l’énergie atomique et aux énergies alternatives Access content directly
Conference Papers Year : 2016

Mechanical behavior at high temperature of highly oxygen- or hydrogen-enriched α and (prior-) $\beta$ phases of zirconium alloys

Abstract

During a hypothetical loss-of-coolant accident (LOCA), zirconium alloy fuel claddings can be loaded by internal pressure and exposed to steam at high temperature (HT, potentially up to 1200°C) until they are cooled and water quenched. A significant fraction of the oxygen reacting with the cladding during oxidation at HT diffuses beneath the oxide through the metallic substrate. This diffusion of oxygen induces a progressive transformation of the metallic $\beta _{Zr}$ phase layer into an intermediate layer of $\alpha _{Zr}$(O) phase containing up to 7 wt.% of oxygen. Furthermore, in some specific conditions, the cladding may rapidly absorb a significant amount of hydrogen during steam exposition at high temperature. Then, hydrogen, as a $\beta _{Zr}$-stabilizer, would mainly diffuse and concentrate up to several thousands of wt.ppm into the inner$\beta _{Zr}$ phase layer
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Dates and versions

cea-02442337 , version 1 (16-01-2020)

Identifiers

  • HAL Id : cea-02442337 , version 1

Cite

I. Turque, R. Chosson, Matthieu Le Saux, J.-C. Brachet, V. Vandenberghe, et al.. Mechanical behavior at high temperature of highly oxygen- or hydrogen-enriched α and (prior-) $\beta$ phases of zirconium alloys. 18th International Symposium on Zirconium in the Nuclear Industry, May 2016, Hilton Head, United States. ⟨cea-02442337⟩
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