A Model of the Relationship between the Parameters of Oxidation of Zirconium Alloys in Water Steam at 1000°C and the Alloy Composition: II. Model Selection, Comparison with Experiment-Reference-Cited by-同舟云学术

A Model of the Relationship between the Parameters of Oxidation of Zirconium Alloys in Water Steam at 1000°C and the Alloy Composition: II. Model Selection, Comparison with Experiment

Published:2021-05 Issue:3 Volume:12 Page:700-706
ISSN:2075-1133
Container-title:Inorganic Materials: Applied Research
language:en
Short-container-title:Inorg. Mater. Appl. Res.

Author:

Kritsky V. G.,Motkova E. A.,Yashin A. S.

Publisher

Pleiades Publishing Ltd

Subject

General Engineering,General Materials Science

Link

https://link.springer.com/content/pdf/10.1134/S2075113321030217.pdf

Reference9 articles.

1. Kritsky, V.G., Motkova, E.A., and Yashin, A.S., A model of the relationship between the oxidation parameters of zirconium alloys in water steam at 1000°C and the alloy composition. I. Data analysis and model development, Fiz. Khim. Obrab. Mater., 2020, no. 2, pp. 58–64.

2. Malgin, A., Markelov, V., Gusev, A., et al., Alloying effect of niobium and tin on the zirconium alloy fuel cladding behavior at high temperature oxidation in steam, Zirconium in the Nuclear Industry: 18th International Symposium, Comstock, R.J. and Motta, A.T., Eds., West Conshohocken, PA: ASTM Int., 2018, pp. 983–1010. https://doi.org/10.1520/STP159720160072

3. Baek, J.H. and Jeong, Y.H., Breakaway phenomenon of Zr-based alloys during a high-temperature oxidation, J. Nucl. Mater., 2008, vol. 372, pp. 152–159.

4. Steinbrück, M., Ver, N., and Große, M., Oxidation of advanced zirconium cladding alloys in steam at temperatures in the range of 600–1200°C, Oxid. Met., 2011, vol. 76, pp. 215–232. https://doi.org/10.1007/s11085-011-9249-3

5. Baek, J.H. and Jeong, Y.H., Steam oxidation of Zr–1.5Nb–0.4Sn–0.2Fe–0.1Cr and Zircaloy-4 at 900–1200°C, J. Nucl. Mater., 2007, vol. 361, pp. 30–40.

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