2020
DOI: 10.1016/j.actamat.2020.08.061
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Phase transformations during cooling from the βZr phase temperature domain in several hydrogen-enriched zirconium alloys studied by in situ and ex situ neutron diffraction

Abstract: In hypothetical accidental conditions, zirconium-based nuclear fuel claddings can absorb high hydrogen contents (up to several thousand wppm) and be exposed to high temperatures (β Zr phase temperature range) before being cooled. This paper thoroughly investigates the microstructural and microchemical evolutions that take place in such

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Cited by 13 publications
(6 citation statements)
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“…Besides, it could be due to the microstructure of the prior-βZr materials tested in this study as a result of the cooling rate applied [41]. However, despite these deviations, the trends are fully consistent.…”
Section: Comparison To Results Obtained On Claddings Oxidized At Htmentioning
confidence: 68%
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“…Besides, it could be due to the microstructure of the prior-βZr materials tested in this study as a result of the cooling rate applied [41]. However, despite these deviations, the trends are fully consistent.…”
Section: Comparison To Results Obtained On Claddings Oxidized At Htmentioning
confidence: 68%
“…The hardening effect of hydrogen in this temperature range would be related to the contribution of zirconium hydrides that extensively precipitate via a eutectoid transition taking place at around 500-550°C [41]. Besides, it may result from a significant amount of hydrogen potentially remaining in solid solution within the Zr matrix, as reported in [41]. However, the hydrogen-related effect appears not to significantly depend on the oxygen content.…”
Section: Yield Stress Ultimate Tensile Strength and Uniform Elongationmentioning
confidence: 84%
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