Effect of water density on the oxidation behavior of alloy A-286 at 625 °C – A TEM study
Source abstract
Abstract
Abstract In this study the effect of water pressure on oxidation behavior of Alloy A-286 is assessed at 625 °C for 1000 h. The pressure values selected are 0.1, 8 and 29 MPa, representing steam, subcritical and supercritical conditions. Transmission electron microscopy (TEM) is used to study the oxide formation on the surface. A-286 sample exposed to supercritical water forms an oxide layer, about 1 μm, containing Fe 2 O 3 , spinel and Cr 2 O 3 . In addition, isolated internal oxidation, up to 10 μm, has taken place during the exposure. Recrystallization of substrate material is also observed. A-286 exposed to steam shows little oxidation. The oxide formed on the surface is only ∼200 nm thick and it is comprised of a top layer of Cr 2 O 3 and a thin sub-layer of SiO 2 , as well as limited grain boundary oxidation in the form of spinel (Cr, Fe, Ti) 3 O 4 and TiO 2 . In contrast, the sample tested under subcritical condition suffered from excessive external and internal oxidation, with about 20 μm of Fe 2 O 3 on the external surface, followed by a partially oxidized zone (up to 20 μm) containing Cr 2 O 3 on the prior grain boundaries and discrete Cr 2 O 3 particles within the grain. The weight gain of A-286 exposed to subcritical condition is several orders of magnitude greater than that seen under steam condition.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: High-Temperature Coating Behaviors · Subcritical and Supercritical Water Processes · Nuclear Materials and Properties
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (36)
Show source-provided references
1. M. Naidin, I. Pioro, R. Duffey, S. Mokry, L. Grande, B. Villamere, L. Allison, A. Rodriguez-Prado, S. Mikhael, K. Chophla, Super Critical Water-cooled Nuclear Reactors (SCWRs) Thermodynamic Cycle Options and Thermal Aspects of Pressure-channel Design, IAEA-CN-164–5S03.
2. Fry · 2002
3. Callister · 2007
4. Oxidation behaviour of austenitic heat-resisting steels in a high temperature and high pressure steam environment10.2355/isijinternational1966.28.761 ↗
5. Corrosion and stress corrosion cracking in supercritical water10.1016/j.jnucmat.2007.05.017 ↗
6. Corrosion tests of candidate fuel cladding and reactor internal structural materials
7. Survey of oxidation in steamside conditions
8. Corrosion of steels and nickel alloys in superheated steam10.1149/1.2425932 ↗
9. Effect of surface preparation on the corrosion of austenitic stainless steel 304L in the high temperature steam and simulated PWR primary water10.1016/j.corsci.2011.12.007 ↗
10. Influence of ageing heat treatment on alloy A-286 microstructure and stress corrosion cracking behaviour in PWR primary water10.1016/j.jnucmat.2006.10.003 ↗
11. Influence of localized deformation on A-286 austenitic stainless steel stress corrosion cracking in PWR primary water10.1016/j.jnucmat.2007.01.001 ↗
12. Focused ion beam microscope
13. Recent advances in FIB TEM specimen preparation techniques10.1016/j.matchar.2005.12.007 ↗
14. Electron energy-loss near-edge structures of 3d transition metal oxides recorded at high-energy resolution10.1016/S0304-3991(03)00109-8 ↗
15. Microstructural aspects and oxidation behavior of laser surface cladded silicon-containing stainless steels10.1016/S1359-6462(97)00528-9 ↗
16. Effect of pressure on the corrosion of materials in high temperature water
17. Effect of surface preparation on the corrosion of austenitic stainless steel 304L in high temperature steam and simulated PWR primary water10.1016/j.corsci.2011.12.007 ↗
18. EFTEM and EELS analysis of the oxide layer formed on HCM12A exposed to SCW10.1016/j.jnucmat.2012.06.017 ↗
19. Corrosion in high temperature and supercritical water and aqueous solution10.1016/S0896-8446(03)00031-7 ↗
20. Corrosion of ferritic-martensitic steels in steam and supercritical water10.1016/j.jnucmat.2012.09.037 ↗
21. Effect of surface treatment on the corrosion of stainless steels in high-temperature water and steam10.1149/1.2423661 ↗
22. Factors controlling corrosion in high-temperature aqueous solutions: a contribution to the dissociation and solubility data influencing corrosion processes10.1016/S0896-8446(99)00009-1 ↗
23. The oxidation behaviour of metals and alloys at high temperatures in atmospheres containing water vapour: a review10.1016/j.pmatsci.2007.11.001 ↗
24. The effect of water-vapour content and gas flow rate on the oxidation mechanism of a 10%Cr-ferritic steel I n Ar-H2O mixtures10.1007/s11085-005-4394-1 ↗
25. M. Kutz, Handbook of Environmental Degradation of Materials, second ed.,Elsevier, p. 163.
26. Barin · 1993
27. The mechanism of high temperature aqueous corrosion of stainless steels10.1016/0010-938X(91)90125-9 ↗
28. Effects of exposure temperature and time on corrosion behaviour of a ferritic-martensitic steel P92 in aerated supercritical water10.1016/j.corsci.2014.10.022 ↗
29. A review of the oxidation behaviour of structural alloys in steam10.1179/095066010X12646898728165 ↗
30. Wrangler · 1985
31. Characterization of transient oxide formation on NiCrAlY after heat treatment in vacuum10.1179/1743294410Y.0000000010 ↗
32. M.G. Fontana, N. D. Greene, Corrosion Engineering, second ed., McGraw-Hill, p. 361.
33. Effect of silicon on the steam oxidation resistance of a 9% Cr heat resistant steel
34. Formation and disapperance of an internal oxidation zone in the initial stage of the steam oxidation of Fe-9Cr-0.26Si ferritic steel at 973K10.1179/mht.2003.014 ↗
35. Effect of Al and Ti addition on the performance of stainless steel 310 in supercritical water10.1179/1743278214Y.0000000225 ↗
36. Material development for supercritical water-cooled reactor