journal article·2017-12

Effects of lead on oxidation behavior of Alloy 690TT within a high temperature aqueous environment

Qiang Hou, Zhiyong Liu, Chengtao Li, Xiaogang Li

Publisher page

Abstract

Abstract The chemical compositions, phases and structures of two oxide films on Alloy 690TT following exposure for 4400 h in pure water with and without lead at 320 °C were studied by surface analysis techniques. The analysis of a lead-doped oxide film prepared by a focused ion beam (FIB) demonstrated that both Cr-rich and Ni-rich oxides were alternatively distributed within the outer layer, whereas the inner layer was porous and poorly protected, causing severe corrosion of the alloy and a thicker film was formed. A duplex film model was proposed for the effects discussion of lead on the oxidation mechanism.
Source: openaire · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: High-Temperature Coating Behaviors · Nuclear Materials and Properties · Hydrogen embrittlement and corrosion behaviors in metals

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (41)

Show source-provided references
1. Inconel Alloy 690-A New Corrosion Resistant Material
2. Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing in pressurized water reactors: part 210.5006/1.3287716 ↗
3. Effects of dissolved calcium and magnesium ions on lead-induced stress corrosion cracking susceptibility of nuclear steam generator tubing alloy in high temperature crevice solutions10.1016/j.electacta.2010.09.104 ↗
4. Intergranular attack and intergranular stress corrosion cracking of Alloy 690 TT in high temperature lead-containing caustic solution10.1002/maco.201005725 ↗
5. Electrochemical interpretation of a stress corrosion cracking of thermally treated Ni base alloys in a lead contaminated water10.4028/www.scientific.net/SSP.124-126.1545 ↗
6. Susceptibility of alloy 690 to stress corrosion cracking in caustic aqueous solutions
7. Trans-twins stress corrosion cracking behaviors of Alloy 690TT in lead-containing caustic solution at 330°C10.1016/j.nucengdes.2011.09.025 ↗
8. Investigation of passive films on nickel Alloy 690 in lead-containing environments10.1016/j.jnucmat.2008.06.037 ↗
9. Effects of pH on lead-induced passivity degradation of nuclear steam generator tubing alloy in high temperature crevice chemistries10.1016/j.electacta.2012.10.006 ↗
10. Oxide properties and stress corrosion cracking behaviour for Alloy 600 in leaded caustic solutions at high temperature10.1016/j.corsci.2010.12.016 ↗
11. A mechanistic study on lead-Induced passivity-degradation of nickel-Based alloy10.1149/1.2741204 ↗
12. Effects of surface state and applied stress on stress corrosion cracking of alloy 690TT in lead-containing caustic solution10.1016/S1005-0302(12)60131-5 ↗
13. Effect of magnesium on the lead induced corrosion and SCC of alloy 800 in neutral crevice solution at high temperature10.1016/j.jnucmat.2009.11.004 ↗
14. Passivity degradation of nuclear steam generator tubing alloy induced by Pb contamination at high temperature10.1016/j.jnucmat.2012.06.021 ↗
15. The mechanism of oxide film formation on Alloy 690 in oxygenated high temperature water10.1016/j.corsci.2011.07.038 ↗
16. Oxidation model for construction materials in supercritical water—Estimation of kinetic and transport parameters
17. Oxidation kinetics and mechanisms of Ni-base alloys in pressurised water reactor primary conditions: influence of subsurface defects10.1016/j.corsci.2011.07.024 ↗
18. On-line monitoring of oxide formation and dissolution on alloy 800H in supercritical water10.1016/j.corsci.2016.05.042 ↗
19. Microstructural characteristics of the oxide films formed on Alloy 690 TT in pure and primary water at 325°C10.1016/j.corsci.2013.06.023 ↗
20. Internal oxidation of Alloy 600 exposed to hydrogenated steam and the beneficial effects of thermal treatment10.1016/j.corsci.2014.04.041 ↗
21. Intergranular oxidation of Ni-based Alloy 600 in a simulated PWR primary water environment10.1016/j.corsci.2016.02.040 ↗
22. Corrosion of nickel-base alloys in primary medium of pressurized water reactors: new insights on the oxide growth mechanisms and kinetic modelling10.1016/j.corsci.2015.09.001 ↗
23. Electrochemical properties and growth mechanism of passive films on Alloy 690 in high-temperature alkaline environments10.1016/j.corsci.2010.06.016 ↗
24. Influence of pH on electrochemical properties of passive films formed on Alloy 690 in high temperature aqueous environments10.1016/j.corsci.2009.08.002 ↗
25. Corrosion behavior of NiCrMo Alloy 625 in high temperature, hydrogenated water10.1016/S0010-938X(02)00230-5 ↗
26. Corrosion behavior of NiCrFe Alloy 600 in high temperature, hydrogenated water10.1016/j.corsci.2005.01.006 ↗
27. K. Fruzzetti, Workshop of Effects of Pb and S on the Performance of Secondary Side Tubing of Steam Generators in PWRs, ANL, IL May 24–27 2005.
28. Correlation between film rupture ductility and PbSCC of Alloy 80010.1016/j.electacta.2007.12.070 ↗
29. Effects of PbO on the oxide films of incoloy 800HT in simulated primary circuit of PWR10.1016/j.jnucmat.2016.02.011 ↗
30. Ex situ and in situ characterization of stress corrosion cracking of nickel-base alloys at high temperature
31. Advanced microstructural characterization of the intergranular oxidation of Alloy 600
32. Sample preparation for atomic-resolution STEM at low voltages by FIB10.1016/j.ultramic.2012.01.005 ↗
33. Development of an in situ Raman spectroscopic system for surface oxide films on metals and alloys in high temperature water10.1016/j.nucengdes.2004.12.002 ↗
34. NIST XPS database. https://srdata.nist.gov/xps/selEnergyType.aspx.
35. A detailed TEM and SEM study of Ni-base alloys oxide scales formed in primary conditions of pressurized water reactor10.1002/sia.5757 ↗
36. Characterization of oxide films formed on alloy 182 in simulated PWR primary water10.1016/j.jnucmat.2009.06.012 ↗
37. Potential-pH diagrams for Pb adsorption on Cu and Ni surfaces at 25°C and 300°C10.1149/2.017303jes ↗
38. 1989 whitney award lecture: toward a more fundamental understanding of corrosion processes10.5006/1.3582030 ↗
39. Condition for lead-induced corrosion of alloy 690 in an alkaline steam generator crevice solution10.5006/1.3319163 ↗
40. Investigation of oxide property on Alloy 600 with the immersion time in a high-temperature leaded alkaline solution10.1007/s12540-014-6009-3 ↗
41. Pourbaix diagrams for the nickel-water system extended to high-subcritical and low-supercritical conditions10.1016/j.corsci.2012.02.007 ↗