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Article Dans Une Revue Journal of Nuclear Materials Année : 2019

Contribution to the understanding of brittle fracture conditions of zirconium alloy fuel cladding tubes during LOCA transient

Résumé

This work addressed fracture mechanisms of nuclear fuel claddings in hypothetical Loss-Of-Coolant-Accident (LOCA) conditions. To this aim, laboratory-scale “semi-integral” thermal-mechanical testswere carried out, using an oxidation temperature of 1200 C, slow cooling down to 700 C and a finalquench by reflooding under an axial load.Two fracture mechanisms were observed. Fracture in the burst zone was due to oxide formation andsubsequent transformation of ductile b into brittle oxygen-enriched a(O). The second fracture mechanismaffected a region both enriched in oxygen and in hydrogen due to secondary hydriding.In the investigated conditions, fracture location was independent of burst morphology, oxidation timeand axial loading. A fracture scenario as a function of the reflooding transient was proposed. Physicalfracture mechanisms were elucidated with respect to microstructural evolution in these two regions.Based on the local distribution of chemical elements and phases, a fracture threshold function of thelocal, layered microstructure was suggested for each fracture location.
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hal-02455379 , version 1 (21-12-2021)

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Paternité - Pas d'utilisation commerciale

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Ronan Thieurmel, Jacques Besson, Édouard Pouillier, Aurore Parrot, Antoine Ambard, et al.. Contribution to the understanding of brittle fracture conditions of zirconium alloy fuel cladding tubes during LOCA transient. Journal of Nuclear Materials, 2019, 527, pp.151815. ⟨10.1016/j.jnucmat.2019.151815⟩. ⟨hal-02455379⟩
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