Analyses of oxide films grown on AISI 304L stainless steel and Incoloy 800HT exposed to supercritical water environment
Source abstract
Abstract
Abstract Supercritical water (SCW) is being considered as a cooling medium for the next generation nuclear reactors because it provides high thermal efficiency and plant simplification. However, materials corrosion has been identified as a critical problem due to the oxidative nature of supercritical water. Thus, for safety using of these nuclear reactor systems a systematic study of candidate materials corrosion is needed. As in other high temperature environments, corrosion in SCW occurs by the growth of an oxide layer on the materials surface. The current work aims to evaluate oxidation behavior of AISI 304L SS and Incoloy 800HT in water at supercritical temperatures in the range 723–873 K under a pressure of 25 MPa for up to 1680 h. After exposure to deaerated supercritical water, the samples were investigated using gravimetry, scanning electron microscopy (SEM), energy dispersive X-ray spectroscopy (EDS), X-ray photoelectron spectroscopy (XPS), and electrochemical impedance spectroscopy (EIS). Oxide films grown on these materials have a layered structure with an outer layer consisting of a mixture of iron oxide/iron–nickel spinel oxides and an inner layer consisting of chromium oxide in the case of Incoloy 800HT and nickel–chromium spinel oxide in the case of AISI 304L SS. The mass gains for Incoloy 800HT at all temperatures were small, while comparatively with AISI 304L SS which exhibited higher oxidation rates. In the same time the results obtained by EIS indicate the best corrosion resistance of oxides grown on Incoloy 800HT surface.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Subcritical and Supercritical Water Processes · High-Temperature Coating Behaviors · Semiconductor materials and devices
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (17)
Show source-provided references
1. A Technology Roadmap for Generation IV Nuclear Energy Systems, Report No. GIF002- 00, December 1, 2002. .
2. J. Buongiorno, W. Corwin, P. MacDonald, L. Mansur, R. Nanstad, R. Swindeman, A. Rowcliffe, G. Was, D. Wilson, I. Wright, Supercritical Water Reactor (SCWR), Survey of Materials Experience and R&D Needs to Assess Viability, INEEL/EXT-03-00693 (Rev. 1), Idaho National Engineering and Environmental Laboratory, 2003.
3. Corwin · Nucl. Eng. Technol. · 2006 · 38 · 591
4. Corrosion behavior of austenitic and ferritic steels in supercritical water10.5516/NET.2008.40.2.147 ↗
5. Zhang · Nucl. Eng. Technol. · 2009 · 41 · 10710.5516/NET.2009.41.1.107 ↗
6. INCOLOY alloy 800H & 800HT, Technical Bulletin, Special Metals Publication SMC-047, 2004. .
7. Fulger · J. Nucl. Mater. · 2009 · 385 · 28810.1016/j.jnucmat.2008.12.004 ↗
8. Kofstad · 1988
9. P.M. Rosecrans, N. Lewis, D.J. Duquette, Effect of corrosion film composition and structure on the corrosion kinetics of Ni–Cr–Fe alloys in high temperature water, Report LM-02K005, 2002.10.2172/821696 ↗
10. Wagner · 1951
11. G.S. Was, P. Ampornrat, G. Gupta, S. Teysseyre, E.A. West, T.R. Allen, K. Sridharan, L. Tan, Y. Chen, X. Ren, C. Pister, Corrosion and stress corrosion cracking in supercritical water, Gen IV Fuels and Materials Topical, ANS Annual Meeting, Reno, Nevada, 2006.10.1016/j.jnucmat.2007.05.017 ↗
12. D. Gómez-Briceño, L. Castro, F. Blázquez, Oxidation and stress corrosion cracking of stainless steels in SCWRs, Workshop on Structural Materials for Innovative Nuclear Systems, Forschungszentrum Karlsruhe, 2007.
13. Robertson · Corros. Sci. · 1991 · 32 · 44310.1016/0010-938X(91)90125-9 ↗
14. Natarajan · Open Corros. J. · 2009 · 2 · 11410.2174/1876503300902010114 ↗
15. Machet · Surf. Interface Anal. · 2002 · 34 · 19710.1002/sia.1282 ↗
16. Tan · J. Nucl. Mater. · 2006 · 348 · 26310.1016/j.jnucmat.2005.09.023 ↗
17. Bruno Yeum, Software Z Simp Win 3.10, EChem Software, Ann Arbor, Michigan, USA, 2001.