journal article·2016-05

The reproducibility of corrosion testing in supercritical water—Results of an international interlaboratory comparison exercise

D. Guzonas, S. Penttilä, W. Cook, W. Zheng, R. Novotny, A. Sáez-Maderuelo, J. Kaneda

Corrosion Science· Volume 106
Publisher page

Abstract

A major challenge in supercritical water-cooled reactor development is the lack of a consistent alloy database. An international interlaboratory comparison test was organized to study the reproducibility of weight change data obtained for identical alloys under similar conditions in different facilities. This paper presents the test procedures, conditions, results, and additional characterization data. More variation in weight change was observed than expected. The scatter was small within the same laboratory, but large between different laboratories. Much of this variation appears to be attributable to differences in test facilities. The data generally agree on the relative ranking of the corrosion resistance.
Source: openaire · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Nuclear Materials and Properties · Advanced Materials Characterization Techniques · Subcritical and Supercritical Water Processes

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References (23)

Show source-provided references
1. B. Cox, Accelerated Oxidation of Zircaloy-2 in Supercritical Steam, Atomic Energy of Canada Limited Report AECL-4448, 1973.
2. Zirconium alloys for supercritical water reactor applications: challenges and possibilities10.1016/j.jnucmat.2007.05.022 ↗
3. Corrosion and deuterium uptake of Zr-based alloys in supercritical water10.1016/j.supflu.2013.03.013 ↗
4. T.R. Allen, Y. Chen, X. Ren, K. Sridharan, L. Tan, G.S. Was, E. West, D.A. Guzonas, Material performance in supercritical water, in: R.J.M. Konings (Ed.), Comprehensive Nuclear Materials, vol. 5, Elsevier, Amsterdam, pp. 279–326.10.1016/B978-0-08-056033-5.00100-2 ↗
5. Effect of Cr and Ni contents on the oxidation behavior of ferritic and austentitic model alloys in air with water vapor10.1023/B:OXID.0000032334.75463.da ↗
6. F.A. Comprelli, D.F. MacMillan, C.N. Spalaris, Materials for superheated fuel sheaths: relative performance of alloys in superheated steam environments, General Electric Company Report GEAP-4351, 1963.
7. Ya. Emel’yanov, O.A. Shatskaya, E.Yu. Rivkin, N.Ya. Nikolenko, Strength of Construction Elements in the Fuel Channels of the Beloyarsk Power Station Reactors Atomnaya Energiya, 33 (1972) 729–733 (in Russian) (Translated in Soviet Atomic Energy 33 (3) (1972) pp. 842–847).10.1007/BF01214529 ↗
8. P.B. Longton, The Oxidation of Iron- and Nickel-based Alloys in Supercritical Steam: A Review of the Available Data, UKAEA The Reactor Group, TRG Report 1144 (C), 1966.
9. Historical experience providing bases for predicting corrosion and stress corrosion in emerging supercritical water nuclear technology: part 1—review10.5006/0726 ↗
10. A review of the oxidation behaviour of structural alloys in steam10.1179/095066010X12646898728165 ↗
11. U.S. program on materials technology for ultra-supercritical coal power plants10.1007/s11665-013-0717-6 ↗
12. D. Guzonas, SCWR Materials and chemistry—status of ongoing research, Proceedings of the GIF Symposium, Paris, France, September 9–10, 2009, 163–172.
13. Water chemistry in a supercritical water-cooled pressure tube reactor10.13182/NT12-A14093 ↗
14. V. Subramanian, J.M. Joseph, H. Subramanian, J.J. Noël, D.A. Guzonas, J.C. Wren, Steady-state radiolysis of supercritical water: model development, predictions and validation, 7th Int. Symposium on Supercritical Water-Cooled Reactors (ISSCWR-7), Helsinki, Finland, 15–18 March, 2015, Paper ISSCWR7-2083.
15. Corrosion of candidate materials for use in a supercritical water CANDU® reactor
16. W. Cook, J. Miles, J. Li, S. Kuyucak, W. Zheng, Preliminary analysis of candidate alloys for use in the CANDU-SCWR, The 2nd Canada–China Joint Workshop on Supercritical Water-Cooled Reactors (CCSC-2010), April 25–28, 2010.
17. High Cr ODS steels performance under supercritical water environment10.1016/j.supflu.2013.04.014 ↗
18. Generation IV material issues—case SCWR10.20965/jdr.2010.p0469 ↗
19. Oxidation of austenitic and ferritic/martensitic alloys in supercritical water10.1016/j.supflu.2013.03.014 ↗
20. J.L. Krausher, W. Zheng, J. Li, D. Guzonas, G. Botton, Filling the gap in SCWR materials research: advanced nuclear corrosion research facilities in Hamilton, 32nd Annual Canadian Nuclear Society Conference, Niagara Falls, ON, June 5–8, 2011.
21. I.G. Wright, P.F. Tortorelli, M. Schütze, Program on Technology Innovation: Oxide Growth and Exfoliation on Alloys Exposed to Steam, Electric Power Research Institute Report 1013666, 2007.
22. Corrosion behavior of steels and nickel alloys in superheated steam10.5006/0010-9312-22.5.147 ↗
23. O.S. Bakai , D.A. Guzonas , V.M. Boriskin , A.M. Dovbnya , S.V. Dyuldya , Combined effect of irradiation, temperature, and water coolant flow on corrosion of Zr-, Ni–Cr-, and Fe–Cr-based alloys, The 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR-7), Helsinki, Finland, 15–18 March, 2015, Paper ISSCWR7-2012.