Characterization of oxides formed on model zirconium alloys in 360°C water using micro-beam synchrotron radiation

A. Yilmazbayhan, Marcelo Gomes Da Silva, Arthur Thompson Motta, Hyun Gil Kim, Yong Hwan Jeong, Jeong Yong Park, Robert Comstock, Barry Lai, Zhounghou Cai

Research output: Chapter in Book/Report/Conference proceedingConference contribution

8 Citations (Scopus)

Abstract

Uniform oxidation by the primary circuit water may limit the service of Zr alloy fuel cladding in Light Water Reactors, especially under more severe fuel duty cycles. Understanding the impact of alloy chemistry and micro structure on corrosion performance may allow us to design better alloys for severe duty cycle applications. To undertake such research, model zirconium alloys (Zr-xCr-yFe, Zr-xCu-yMo, Zr-xSn and ZrxNb, with various values of x and y) were corroded at 360°C in pure water to help isolate the role of individual alloying elements on the oxide formation process. The structure of the protective oxide, believed to be the cause for the different corrosion behavior of different zirconium alloys, was investigated using microbeam synchrotron radiation diffraction. Experiments were conducted at both the Advanced Photon Source in the USA using a 0.25 micron beam, and in the Pohang Light Source, Korea, using a 1.25 micron beam. Such micro-diffraction experiments allow the determination of phases present, oxide texture, grain size and accumulated stress, as a function of distance from the oxide-metal interface. Additional examinations were performed using cross-sectional transmission electron microscopy (TEM). The results of this examination show heretofore unobserved details of the oxide-metal interface and of the variation of phase content with distance from oxide-metal interface and overall oxide thickness. We focus in this paper on the evolution of oxide texture and phase content, between the different model alloys to help elucidate the role of individual alloying elements on the oxide formation process.

Original languageEnglish (US)
Title of host publicationProceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
Pages201-212
Number of pages12
StatePublished - Dec 1 2005
Event12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors - Salt Lake City, UT, United States
Duration: Aug 14 2005Aug 18 2005

Publication series

NameProceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors

Other

Other12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
CountryUnited States
CitySalt Lake City, UT
Period8/14/058/18/05

Fingerprint

Zirconium alloys
Synchrotron radiation
Oxides
Water
Alloying elements
Light sources
Textures
Diffraction
Metals
Corrosion
Light water reactors
Photons
Experiments
Transmission electron microscopy
Oxidation
Microstructure
Networks (circuits)

All Science Journal Classification (ASJC) codes

  • Engineering(all)

Cite this

Yilmazbayhan, A., Da Silva, M. G., Motta, A. T., Kim, H. G., Jeong, Y. H., Park, J. Y., ... Cai, Z. (2005). Characterization of oxides formed on model zirconium alloys in 360°C water using micro-beam synchrotron radiation. In Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (pp. 201-212). (Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors).
Yilmazbayhan, A. ; Da Silva, Marcelo Gomes ; Motta, Arthur Thompson ; Kim, Hyun Gil ; Jeong, Yong Hwan ; Park, Jeong Yong ; Comstock, Robert ; Lai, Barry ; Cai, Zhounghou. / Characterization of oxides formed on model zirconium alloys in 360°C water using micro-beam synchrotron radiation. Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. 2005. pp. 201-212 (Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors).
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abstract = "Uniform oxidation by the primary circuit water may limit the service of Zr alloy fuel cladding in Light Water Reactors, especially under more severe fuel duty cycles. Understanding the impact of alloy chemistry and micro structure on corrosion performance may allow us to design better alloys for severe duty cycle applications. To undertake such research, model zirconium alloys (Zr-xCr-yFe, Zr-xCu-yMo, Zr-xSn and ZrxNb, with various values of x and y) were corroded at 360°C in pure water to help isolate the role of individual alloying elements on the oxide formation process. The structure of the protective oxide, believed to be the cause for the different corrosion behavior of different zirconium alloys, was investigated using microbeam synchrotron radiation diffraction. Experiments were conducted at both the Advanced Photon Source in the USA using a 0.25 micron beam, and in the Pohang Light Source, Korea, using a 1.25 micron beam. Such micro-diffraction experiments allow the determination of phases present, oxide texture, grain size and accumulated stress, as a function of distance from the oxide-metal interface. Additional examinations were performed using cross-sectional transmission electron microscopy (TEM). The results of this examination show heretofore unobserved details of the oxide-metal interface and of the variation of phase content with distance from oxide-metal interface and overall oxide thickness. We focus in this paper on the evolution of oxide texture and phase content, between the different model alloys to help elucidate the role of individual alloying elements on the oxide formation process.",
author = "A. Yilmazbayhan and {Da Silva}, {Marcelo Gomes} and Motta, {Arthur Thompson} and Kim, {Hyun Gil} and Jeong, {Yong Hwan} and Park, {Jeong Yong} and Robert Comstock and Barry Lai and Zhounghou Cai",
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Yilmazbayhan, A, Da Silva, MG, Motta, AT, Kim, HG, Jeong, YH, Park, JY, Comstock, R, Lai, B & Cai, Z 2005, Characterization of oxides formed on model zirconium alloys in 360°C water using micro-beam synchrotron radiation. in Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, pp. 201-212, 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Salt Lake City, UT, United States, 8/14/05.

Characterization of oxides formed on model zirconium alloys in 360°C water using micro-beam synchrotron radiation. / Yilmazbayhan, A.; Da Silva, Marcelo Gomes; Motta, Arthur Thompson; Kim, Hyun Gil; Jeong, Yong Hwan; Park, Jeong Yong; Comstock, Robert; Lai, Barry; Cai, Zhounghou.

Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. 2005. p. 201-212 (Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

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T1 - Characterization of oxides formed on model zirconium alloys in 360°C water using micro-beam synchrotron radiation

AU - Yilmazbayhan, A.

AU - Da Silva, Marcelo Gomes

AU - Motta, Arthur Thompson

AU - Kim, Hyun Gil

AU - Jeong, Yong Hwan

AU - Park, Jeong Yong

AU - Comstock, Robert

AU - Lai, Barry

AU - Cai, Zhounghou

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N2 - Uniform oxidation by the primary circuit water may limit the service of Zr alloy fuel cladding in Light Water Reactors, especially under more severe fuel duty cycles. Understanding the impact of alloy chemistry and micro structure on corrosion performance may allow us to design better alloys for severe duty cycle applications. To undertake such research, model zirconium alloys (Zr-xCr-yFe, Zr-xCu-yMo, Zr-xSn and ZrxNb, with various values of x and y) were corroded at 360°C in pure water to help isolate the role of individual alloying elements on the oxide formation process. The structure of the protective oxide, believed to be the cause for the different corrosion behavior of different zirconium alloys, was investigated using microbeam synchrotron radiation diffraction. Experiments were conducted at both the Advanced Photon Source in the USA using a 0.25 micron beam, and in the Pohang Light Source, Korea, using a 1.25 micron beam. Such micro-diffraction experiments allow the determination of phases present, oxide texture, grain size and accumulated stress, as a function of distance from the oxide-metal interface. Additional examinations were performed using cross-sectional transmission electron microscopy (TEM). The results of this examination show heretofore unobserved details of the oxide-metal interface and of the variation of phase content with distance from oxide-metal interface and overall oxide thickness. We focus in this paper on the evolution of oxide texture and phase content, between the different model alloys to help elucidate the role of individual alloying elements on the oxide formation process.

AB - Uniform oxidation by the primary circuit water may limit the service of Zr alloy fuel cladding in Light Water Reactors, especially under more severe fuel duty cycles. Understanding the impact of alloy chemistry and micro structure on corrosion performance may allow us to design better alloys for severe duty cycle applications. To undertake such research, model zirconium alloys (Zr-xCr-yFe, Zr-xCu-yMo, Zr-xSn and ZrxNb, with various values of x and y) were corroded at 360°C in pure water to help isolate the role of individual alloying elements on the oxide formation process. The structure of the protective oxide, believed to be the cause for the different corrosion behavior of different zirconium alloys, was investigated using microbeam synchrotron radiation diffraction. Experiments were conducted at both the Advanced Photon Source in the USA using a 0.25 micron beam, and in the Pohang Light Source, Korea, using a 1.25 micron beam. Such micro-diffraction experiments allow the determination of phases present, oxide texture, grain size and accumulated stress, as a function of distance from the oxide-metal interface. Additional examinations were performed using cross-sectional transmission electron microscopy (TEM). The results of this examination show heretofore unobserved details of the oxide-metal interface and of the variation of phase content with distance from oxide-metal interface and overall oxide thickness. We focus in this paper on the evolution of oxide texture and phase content, between the different model alloys to help elucidate the role of individual alloying elements on the oxide formation process.

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M3 - Conference contribution

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BT - Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors

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Yilmazbayhan A, Da Silva MG, Motta AT, Kim HG, Jeong YH, Park JY et al. Characterization of oxides formed on model zirconium alloys in 360°C water using micro-beam synchrotron radiation. In Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. 2005. p. 201-212. (Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors).