Oxidation behavior of β-Nb precipitates in Zr–1Nb–0.2Bi alloy corroded in lithiated water at 360 °C
Source abstract
Abstract
Abstract The oxidation behavior of β-Nb precipitates in Zr–1Nb–0.2Bi alloy corroded in lithiated water with 0.01 M LiOH at 360 °C/18.6 MPa was investigated by high-resolution transmission electron microscopy (HRTEM). From the HRTEM observation and the analysis for the oxide layer, the oxidation behavior of β-Nb precipitates corroded in lithiated water in early stage is as follows: β-Nb precipitates are first oxidized to NbO 2 , then part of it is further oxidized to Nb 2 O 5 in some specific crystallographic orientations. The reason for accelerated corrosion of Zr–Nb alloys in lithiated water is discussed from the rapid oxidation of β-Nb precipitates.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · High Temperature Alloys and Creep
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (38)
Show source-provided references
1. A study of the interphase structure at the oxide-metal interface in the corrosion of zirconium-based alloys10.1016/0010-938X(94)90157-0 ↗
2. Grain morphology and crystal structure of pre-transition oxides formed on Zircaloy-410.1016/j.corsci.2013.05.007 ↗
3. Sn–Zr10.1007/s11669-010-9734-4 ↗
4. Ternery Zr–Nb–Fe (O) system: phase diagram at 853K and corrosion behavior in the domain Nb<0. 8%10.1016/j.jnucmat.2004.01.007 ↗
5. Corrosion and microstructural characteristics of Zr–Nb alloys with different Nb contents10.1016/j.jnucmat.2007.05.035 ↗
6. Effect of adding Cu on the corrosion resistance of M5 alloy in super-heated steam at 500°C
7. Effect of Bi addition on the corrosion resistance of Zr-4 in superheated steam at 400°C /10.3MPa10.3724/SP.J.1037.2012.00176 ↗
8. Eucken · 1989 · 1023 · 113
9. Optimization of N18 zirconium alloy for fuel cladding of water reactors10.1016/S1005-0302(12)60105-4 ↗
10. Mardon · 2000 · 1354 · 505
11. Sabol · 1989 · 1023 · 227
12. Analysis of oxidation behavior of the β-Nb phase formed in Zr–1.5Nb alloy by using the HVEM10.1016/j.jallcom.2009.03.144 ↗
13. Oxidation behavior of β-Nb phase precipitated in Zr–2.5Nb alloy
14. Oxidation of β-Nb and Zr(Fe, V)2 precipitates in oxide films formed on advanced Zr-based alloys10.1016/S0022-3115(99)00253-6 ↗
15. Oxidation behaviour of zirconium alloys and their precipitates –A mechanistic study10.1016/j.jnucmat.2012.06.026 ↗
16. On the mechanism of oxidation of Zr–1%Nb alloy in pressurized steam10.1016/S0010-938X(71)80011-2 ↗
17. Nikulina · 1996 · 1295 · 785
18. Oxidation properties of Zr–Nb alloys at 500–600°C under low oxygen potentials10.1016/j.corsci.2004.06.011 ↗
19. Kinetics of oxidation of Zr–1%Nb alloy in pressurized steam and air at 400–700°C10.1016/S0010-938X(69)80052-1 ↗
20. Influence of water chemistry on the corrosion mechanism of a zirconium–niobium alloy in simulated light water reactor coolant conditions10.1016/j.corsci.2009.08.045 ↗
21. Effect of Bi addition on the corrosion resistance of Zr–1Nb alloy in deionized water at 360°C and 18.6MPa10.3724/SP.J.1037.2012.00378 ↗
22. Sample preparation for atomic-resolution STEM at low voltages by FIB10.1016/j.ultramic.2012.01.005 ↗
23. IAEA-TECDOC-996 · 1998 · 40
24. On the evolution of wave structure at the metal/oxide interface during oxidation of Zr alloys10.1016/j.corsci.2014.07.002 ↗
25. Method of elastic energy minimization for evaluation of transition parameters in oxidation kinetics of Zr alloys10.1016/j.corsci.2012.04.035 ↗
26. Investigation of oxide layers formed on Zircaloy-4 coarse-grained specimens corroded at 360°C in lithiated aqueous solution10.1016/j.corsci.2014.12.012 ↗
27. Niobium speciation at the metal/oxide interface of corroded niobium-doped Zircaloys: A X-ray absorption near-edge structure study10.1016/j.corsci.2008.01.011 ↗
28. Origin and effect of lateral cracks in oxide scales formed on zirconium alloys10.1016/j.jnucmat.2012.06.039 ↗
29. The effects of water chemistry and composition on the microstructure evolution of oxide films on zirconium alloys during autoclave tests
30. Zhou · 1505 · 2009 · 360
31. Microstructure of oxide films formed on Zircaloy-4
32. Microstructure evolution of oxide films formed on Zircaloy-4 during autoclave tests
33. Vittoz · Sci. Technol. · 1999 · 13 · 1045
34. Deuterium diffusion in LiOH–water-corroded oxide layer of zirconium alloys10.1016/j.pnucene.2011.11.009 ↗
35. Focused ion beam sectioning for the 3D characterisation of cracking in oxide scales formed on commercial ZIRLO™ alloys during corrosion in high temperature pressurised water10.1016/j.corsci.2011.08.013 ↗
36. Oxidation behavior of binary zirconium alloys containing intermetallic precipitates10.1016/j.jnucmat.2010.11.099 ↗
37. Preuss · 2011 · 1529 · 649
38. Multiple rate transitions in the aqueous corrosion of Zircaloy10.1149/1.2425526 ↗