Effects of irradiation on the oxidation of zirconium alloys in high temperature aqueous environments

Cox, B.

doi:10.1016/0022-3115(68)90055-x

Cited by 71 publications

(5 citation statements)

References 24 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…First, oxygen in the water molecule dissociates and is adsorbed onto the oxide layer surface at an oxygen vacancy site. Because of the defect concentration gradient [the oxide is substoichiometric at the oxide/metal interface (30)] and the electric potential across the oxide [resulting from ambipolar diffusion (31) and the space charge in the oxide (32,33)], the oxygen anions diffuse either through the bulk of the oxide or along the oxide grain boundaries via solid-state diffusion (34,35). When the oxygen anion reaches the oxide/metal interface, it reacts with zirconium cations to form new oxide.…”

Section: Figurementioning

confidence: 99%

Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding

Motta

Couet

Comstock

2015

Annu. Rev. Mater. Res.

367

149

View full text Add to dashboard Cite

During operation, nuclear fuel rods are immersed in the primary water, causing waterside corrosion and consequent hydrogen ingress. In this review, the mechanisms of corrosion and hydrogen pickup and the role of alloy selection in minimizing both phenomena are considered on the basis of two principal characteristics: the pretransition kinetics and the loss of oxide protectiveness at transition. In zirconium alloys, very small changes in composition or microstructure can cause significant corrosion differences so that corrosion performance is strongly alloy dependent. The alloys show different, but reproducible, subparabolic pretransition kinetics and transition thicknesses. A mechanism for oxide growth and breakup based on a detailed study of the oxide structure can explain these results. Through the use of the recently developed coupled current charge compensation model of corrosion kinetics and hydrogen pickup, the subparabolic kinetics and the hydrogen fraction can be rationalized: Hydrogen pickup increases when electron transport decreases, requiring hydrogen ingress to close the reaction.

show abstract

Section: Figurementioning

confidence: 99%

Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding

Motta

Couet

Comstock

2015

Annu. Rev. Mater. Res.

367

149

View full text Add to dashboard Cite

show abstract

“…41 , 44 The vast research work conducted over the years has led to some understanding of these problems: contrary to the expectation that irradiation-induced defects can cause breakdown of the protective fi lm on Zircaloy clads, 45 the examinations of irradiated clads did not show any evidence of oxide damage; 46 , 47 though the exact mechanism of lithium induced corrosion of zirconium is not clear, the general understanding of the lithium effect is that Li gets incorporated in solid solution in the ZrO 2 and alters the vacancy concentration and distribution in the oxide fi lm; since zirconium alloy corrosion proceeds by oxygen diffusion through the fi lm, the increased number of vacancies should increase the diffusion and, hence, the corrosion rate; further, it has always been noted in irradiated Zircaloys that hydride density is high in locations where the oxide thickness is high; this clearly indicates that the cathodic hydriding and anodically favoured oxidation occur independent of each other. Change in fabrication route, which can result in the second phase with a different composition, can reduce the susceptibility to nodular corrosion but can lead to increased uniform corrosion.…”

Section: © Woodhead Publishing Limited 2013mentioning

confidence: 95%

Overview of ageing and degradation issues in light water reactors (LWRs)

Murty

Ramaswamy

2013

Materials Ageing and Degradation in Light Water Reactors

View full text Add to dashboard Cite

“…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.

View full text Add to dashboard Cite

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.

show abstract

Effects of irradiation on the oxidation of zirconium alloys in high temperature aqueous environments

Cited by 71 publications

References 24 publications

Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding

Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding

Overview of ageing and degradation issues in light water reactors (LWRs)

Effects of Radiation-Induced Defects on Corrosion

Contact Info

Product

Resources

About