The modeling of the hydrogen solid solubility hysteresis in zirconium alloys

Kolesnik, M.; Aliev, T.; Likhanskiǐ, V. V.

doi:10.1016/j.actamat.2019.07.044

Cited by 18 publications

(2 citation statements)

References 24 publications

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“…The large dilatational misfit is sufficient to cause the emission of dislocations and dislocation loops in Zr matrices, accompanied by hydride precipitation [ 14 ]. Additionally, the movement of the hydride–matrix-phase interface also dissipates energy [ 15 ]. These two factors combine to delay hydride precipitation and cause TSSP to be significantly higher than TSSD ( Figure 1 ).…”

Section: Hydride Nucleation and Growth Behaviorsmentioning

confidence: 99%

Mechanisms of Hydride Nucleation, Growth, Reorientation, and Embrittlement in Zirconium: A Review

Jia

Han

2023

Materials

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Zirconium (Zr) hydrides threaten the reliability of fuel assembly and have repeatedly induced failures in cladding tubes and pressure vessels. Thus, they attract a broad range of research interests. For example, delayed hydride cracking induced a severe fracture and failure in a Zircaloy-2 pressure tube in 1983, causing the emergency shutdown of the Pickering nuclear reactor. Hydride has high hardness and very low toughness, and it tends to aggregate toward cooler or tensile regions, which initiates localized hydride precipitation and results in delayed hydride cracking. Notably, hydride reorientation under tensile stress substantially decreases the fracture toughness and increases the ductile-to-brittle transition temperature of Zr alloys, which reduces the safety of the long-term storage of spent nuclear fuel. Therefore, improving our knowledge of Zr hydrides is useful for effectively controlling hydride embrittlement in fuel assembly. The aim of this review is to reorganize the mechanisms of hydride nucleation and growth behaviors, hydride reorientation under external stress, and hydride-induced embrittlement. We revisit important examples of progress of research in this field and emphasize the key future aspects of research on Zr hydrides.

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Section: Hydride Nucleation and Growth Behaviorsmentioning

confidence: 99%

Mechanisms of Hydride Nucleation, Growth, Reorientation, and Embrittlement in Zirconium: A Review

Jia

Han

2023

Materials

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“…Zirconium alloys possess a good combination of high corrosion resistance and neutron economy [3,4], which makes them suitable for production of cladding tubes for water cooled reactors. One of the important aspects of cladding tubes is the great influence of fretting corrosion on the service behavior of these materials.…”

Section: Introductionmentioning

confidence: 99%