The effects of radiation and oxygen on the aqueous oxidation of zirconium and its alloys at 290 °c

Bradhurst, D.H.; Shirvington, P.J.; Heuer, P.M.

doi:10.1016/0022-3115(73)90122-0

Cited by 33 publications

(5 citation statements)

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“…The opposite effects of niobium and lithium on energy transfer in the ZrO 2 /H 2 O system may have a similar mechanistic basis as the known opposite effects of those elements on the radiation-induced oxidation of zirconium-based alloys in high temperature water. From many tested Zr-based alloys and pure zirconium, only niobium-doped materials typically show no radiation enhancement of oxidation in high-temperature water. , TL experiments 41 show that niobium incorporates into the ZrO 2 oxide film onto those alloys and remarkably effects lifetimes and migration distances of the electronic excitations created by irradiation. On the other hand, LiOH dosing into water is known as a promoter of Zircaloy cladding oxidation due to incorporation of Li + cations into the protective ZrO 2 oxide film .…”

Section: Discussionmentioning

confidence: 99%

“…From many tested Zr-based alloys and pure zirconium, only niobium-doped materials typically show no radiation enhancement of oxidation in high-temperature water. 78,79 TL experiments 41 show that niobium incorporates into the ZrO 2 oxide film onto those alloys and remarkably effects lifetimes and migration distances of the electronic excitations created by irradiation. On the other hand, LiOH dosing into water is known as a promoter of Zircaloy cladding oxidation due to incorporation of Li + cations into the protective ZrO 2 oxide film.…”

Section: Discussionmentioning

confidence: 99%

“…80 Such behavior may be another indication of the important role that water radiolysis plays in the corrosion enhancement of zirconiumbased nuclear fuel cladding. 78,[80][81][82][83][84][85][86] According to the data presented in this work, radiolysis of water coolant should be enhanced near the fuel cladding surface due to energy transfer from the zirconium oxide. The energy transfer is very sensitive to the presence of Nb 5+ or Li + incorporated into the protective ZrO 2 film.…”

Section: Discussionmentioning

confidence: 99%

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Interfacial Energy Transfer during Gamma Radiolysis of Water on the Surface of ZrO₂ and Some Other Oxides

2001

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The effect of an oxide interface on 60 Co gamma radiolysis of water molecules was studied. On the basis of the molecular hydrogen yield when compared with the radiolysis of the control ampules without oxides, all the tested materials can be generally classified into three groups: I. Oxides that lower the H 2 yield (MnO 2 , Co 3 O 4 , CuO, and Fe 2 O 3 ); II. Oxides with H 2 yields that are close to G values obtained in control experiments

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Section: Discussionmentioning

confidence: 99%

Section: Discussionmentioning

confidence: 99%

Section: Discussionmentioning

confidence: 99%

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Interfacial Energy Transfer during Gamma Radiolysis of Water on the Surface of ZrO₂ and Some Other Oxides

2001

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“…For both Zircaloy-2 and Zr-2.5%Nb, Asher et al (88) observed a strong enhancement of radiation-induced corrosion with increasing dissolved oxygen content. Bradhurst et al (95) demonstrated that the simultaneous presence of oxygen and radiation is necessary to increase corrosion rates. To suppress the effects of O 2− production via radiolysis, modern reactors operate with deoxygenated and hydrogenated water.…”

Section: Zr-based Alloy Corrosion In Watermentioning

confidence: 99%

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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“…In a steam environment at high temperature and pressure, in water with a high oxygen content or in steam with hydrogen overpressure, nodular oxide is formed on Zircaloy [18,22,24,29,[56][57][58][59]. In a steam environment at high temperature and pressure, in water with a high oxygen content or in steam with hydrogen overpressure, nodular oxide is formed on Zircaloy [18,22,24,29,[56][57][58][59].…”

Section: Nodular Corrosionmentioning

confidence: 99%

Corrosion of Zr Alloys in Water and Steam

1994

Materials Science Monographs

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The oxide, Zr0 2 , is formed by the reaction of Zr with water. Water molecules dissociate on the oxide surface, the oxygen formed diffuses through anion vacancies in the oxide to the metal-oxide boundary, where part of the oxygen dissolves in the metal and part reacts to form new oxide. As the oxide has a greater volume than the metal from which it was formed, strain is produced at the boundary. Hydrogen formed in the reaction partly diffused through the oxide into the metal.The process of oxidation of Zr and its alloys in water and steam passes through several stages with correspondingly different laws for the rate of oxide growth as a function of temperature and the corrosion exposure time. In the initial stage, especially at low temperatures, the oxide growth has a complex character, controlled by either a logarithmic or parabolic rate law. This period is a result of localized oxidation of the grain boundaries and of intermetallic species, preferential oxidation of some grains, etc.At temperatures above 300 °C, the oxidation rate is controlled by a cubic or parabolic law. Black, adhering and non-stoichiometric Zr0 2 is also formed. After a certain period of time, given by the oxidation conditions, a change occurs in the oxidation kinetics, appearing as a break on the kinetic curves, after which the oxidation kinetics obey a linear law. This is mostly accompanied by the formation of white or light grey (light brown) oxide, that adheres poorly to the metal and peels off.The increase in the mass of the Zr alloys sample with time can be expressed by the relationship ΔΜ = kt n (9.1)where Am is the mass increase per unit surface area, t is the oxidation time, k is the oxidation rate constant, and n is a dimensionless coefficient. The corrosion process is affected by a great many factors, the most important of which are: the chemical composition of the Zr alloy, both alloying elements and impurities in the metal, the metal structure determined by the technology of alloy working, the quality of the alloy surface, determined by the technology, the composition of the corrosive medium, the influence of radiation, especially the flux and the fluence of fast neutrons. 9.

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The effects of radiation and oxygen on the aqueous oxidation of zirconium and its alloys at 290 °c

Cited by 33 publications

References 13 publications

Interfacial Energy Transfer during Gamma Radiolysis of Water on the Surface of ZrO₂ and Some Other Oxides

Interfacial Energy Transfer during Gamma Radiolysis of Water on the Surface of ZrO₂ and Some Other Oxides

Effects of Radiation-Induced Defects on Corrosion

Corrosion of Zr Alloys in Water and Steam

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The effects of radiation and oxygen on the aqueous oxidation of zirconium and its alloys at 290 °c

Cited by 33 publications

References 13 publications

Interfacial Energy Transfer during Gamma Radiolysis of Water on the Surface of ZrO2 and Some Other Oxides

Interfacial Energy Transfer during Gamma Radiolysis of Water on the Surface of ZrO2 and Some Other Oxides

Effects of Radiation-Induced Defects on Corrosion

Corrosion of Zr Alloys in Water and Steam

Contact Info

Product

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Interfacial Energy Transfer during Gamma Radiolysis of Water on the Surface of ZrO₂ and Some Other Oxides

Interfacial Energy Transfer during Gamma Radiolysis of Water on the Surface of ZrO₂ and Some Other Oxides