Corrosion of Zirconium Alloys

Allen, Todd R.; Konings, R.J.M.; Motta, Arthur T.; Couet, Adrien

doi:10.1016/b978-0-12-803581-8.11708-4

Cited by 6 publications

(4 citation statements)

References 163 publications

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“…Furthermore, radiation damage leads to microstructural changes, the redistribution of alloying elements, and the concomitant development of internal stresses that should also modify corrosion. Yet, as discussed by Cox (42) and more recently by Allen et al (43), there appears to be no evidence that neutron-induced defects in the oxide layer directly enhance oxygen diffusion in Zircaloys; instead, neutron-induced precipitate dissolution appears to be dominant.…”

Section: Discussionmentioning

confidence: 98%

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Effects of Radiation-Induced Defects on Corrosion

Schmidt

Hosemann

Scarlat

et al. 2021

Annu. Rev. Mater. Res.

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The next generation of nuclear reactors will expose materials to conditions that, in some cases, are even more extreme than those in current fission reactors, inevitably leading to new materials science challenges. Radiation-induced damage and corrosion are two key phenomena that must be understood both independently and synergistically, but their interactions are often convoluted. In the light water reactor community, a tremendous amount of work has been done to illuminate irradiation-corrosion effects, and similar efforts are under way for heavy liquid metal and molten salt environments. While certain effects, such as radiolysis and irradiation-assisted stress corrosion cracking, are reasonably well established, the basic science of how irradiation-induced defects in the base material and the corrosion layer influence the corrosion process still presents many unanswered questions. In this review, we summarize the work that has been done to understand these coupled extremes, highlight the complex nature of this problem, and identify key knowledge gaps. Expected final online publication date for the Annual Review of Materials Science, Volume 51 is August 2021. Please see http://www.annualreviews.org/page/journal/pubdates for revised estimates.

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Section: Discussionmentioning

confidence: 98%

“…Zircaloy corrosion has been extensively studied and reviewed (40)(41)(42)(43). As fuel cladding, this material must form a thin protective oxide to retain structural integrity without compromising the cladding's heat transfer capabilities.…”

Section: Aqueousmentioning

confidence: 99%

Effects of Radiation-Induced Defects on Corrosion

Schmidt

Hosemann

Scarlat

et al. 2021

Annu. Rev. Mater. Res.

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“…Zirconium alloys are a preferred material for commercial pressurized water reactor fuel cladding due to their exceptional corrosion resistance, mechanical properties, and thermal neutron economy. However, zirconium alloys readily absorb hydrogen through oxidation reactions with cooling water [1]. The solubility of hydrogen in zirconium alloys is relatively low, approximately 80 ppm at 300 • C and 200 ppm at 400 • C. Consequently, exceeding the solubility limit leads to the precipitation of brittle zirconium hydride [2].…”

Section: Introductionmentioning

confidence: 99%

Effects of Hydrogenation on the Corrosion Behavior of Zircaloy-4

Yue,

Zhou,

Zhao

et al. 2024

Materials

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Hydrogen plays an important role in the corrosion of zirconium alloys, and the degree of influence highly depends on the alloy composition and conditions. In this work, the effects of hydrogenation on the corrosion behavior of Zircaloy-4 in water containing 3.5 ppm Li + 1000 ppm B at 360 °C/18.6 MPa were investigated. The results revealed that hydrogenation can shorten the corrosion transition time and increase the corrosion rates of Zircaloy-4. The higher corrosion rates can be ascribed to the larger stress in the oxide film of hydrogenated samples, which can accelerate the evolution of the microstructure of the oxide film. In addition, we also found that hydrogenation has little effect on the t-ZrO2 content in the oxide film and there is no direct correspondence between the t-ZrO2 content and the corrosion resistance of the Zircaloy-4.

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“…Zirconium alloys are widely used in the nuclear industry because of their low absorption crosssection for thermal neutrons (Onimus et al, 2020b). Furthermore, thanks to alloying elements and careful microstructure control, optimized zirconium alloys exhibit a very good corrosion resistance (Allen et al, 2020;Tewari et al, 2020). They are therefore very well suited as cladding tubes or structure components in light or heavy water nuclear reactors.…”

Section: -Introductionmentioning

confidence: 99%