The progress of SPP oxidation in zircaloy-4 and its relation to corrosion and hydrogen pickup
Source abstract
Abstract
Abstract The evolution of Cr and Fe within the oxide formed on Zircaloy-4 in high-temperature pure water and a high-pH aqueous environment has been followed in detail by electron energy loss spectroscopy (EELS). The oxidation states of Cr, Fe and Zr have been determined as a function of exposure time and location in the oxide film. Much Cr and all the Fe diffuse out of the original Laves phase and precipitate within cracks or on the outer oxide surface. Cr oxidation is complete prior to transition; Fe oxidation occurs mainly after transition. The different hypotheses concerning the mechanisms by which the alloying elements influence oxidation and hydrogen pickup are examined in the light of this information. The mechanisms which agree with these observations include: doping of the bulk ZrO2 by low levels of alliovalent cations; doping ZrO2 grain boundaries with alliovalent cations; injection of holes into near-surface oxide by islands of Fe2O3; reaction of water with islands of metallic Fe (and Ni) on surfaces of internal cracks around transition; control of transition by mechanical properties
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Radioactive element chemistry and processing · Electronic and Structural Properties of Oxides
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (45)
Show source-provided references
1. Rickover · 1975
2. The development and applications of zirconium alloys10.1016/0261-3069(85)90165-7 ↗
3. ZIRLO(TM) - an alloy development success
4. Current status of materials development of nuclear fuel cladding tubes for light water reactors10.1016/j.nucengdes.2017.02.031 ↗
5. Influence of transition elements Fe, Cr and V on long-time corrosion in PWRs
6. Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys
7. Role of the second phase particles in zirconium binary alloys
8. Behaviour of structural materials for fuel and control elements in light water cooled power reactors
9. Microstructure and properties of zirconium alloys in the absence of irradiation
10. Role of iron for hydrogen absorption mechanism in zirconium alloys
11. Corrosion-electrochemical properties of zirconium intermetallics
12. Examinations of the corrosion mechanism of zirconium alloys
13. Cox · 1993
14. Precipitate behaviour in zircaloy-2 oxide films and its relevance to corrosion resistance
15. Redistribution of the alloying elements during Zircaloy-2 oxidation
16. Chapter 2
17. A study of charge transport processes during the oxidation of zirconium alloys
18. Accommodation of tin in tetragonal ZrO210.1063/1.4909505 ↗
19. The effect of Nb on the corrosion and hydrogen pickup of Zr alloys10.1016/j.actamat.2017.04.063 ↗
20. Modelling and experimental analysis of the effect of solute iron in thermally grown Zircaloy-4 oxides
21. Role of iron for hydrogen absorption mechanism in zirconium alloys10.1520/JAI12352 ↗
22. The role of space charge in the oxidation of Zircaloy-4 between 350 and 450C i nair
23. The coupled current charge compensation model for zirconium alloy fuel cladding oxidation: I. Parabolic oxidation of zirconium alloys10.1016/j.corsci.2015.07.003 ↗
24. Toward a comprehensive mechanistic understanding of hydrogen uptake in zirconium alloys by combining atom probe analysis with electronic structure calculatins
25. Oxidation behaviour of zirconium alloys and their precipitates - A mechanistic study
26. Oxidation behaviour of binary zirconium alloys containing intermetallic precipitates
27. The corrosion of Zr(Fe,Cr)2 and Zr2Fe second phase particles in Zircaloy-4 under 350°C pressurised water conditions10.1016/j.corsci.2017.09.014 ↗
28. Precipitate evolution in the Zircaloy-4 oxide layer
29. Oxidation of intermetallic precipitates in zircaloy-4: impact of irradiation
30. Ives · 1969
31. Standard Test method for Corrosion Testing of Products of Zirconium, Hafnium and their Alloys in Water at 680°F or in Steam at 750°F, ASTM G2/G2M-06, ASTM, 2011.
32. TEM sample preparation and damage10.1557/mrs2007.63 ↗
33. Determination of chromium valence over the range Cr(0) - Cr(VI) by electron energy loss spectroscopy10.1016/j.ultramic.2006.02.005 ↗
34. Reliable method for determining the oxidation state in chromium oxides10.1021/ic901887y ↗
35. Oxidation state and chemical shift investigation in transition metal oxides by EELS10.1016/j.ultramic.2012.03.002 ↗
36. Electron-energy-loss-spectroscopy near-edge fine structures in the iron-oxygen system10.1103/PhysRevB.44.11402 ↗
37. Study of the L23 edges in the 3d transition metals and their oxides by electron-energy-loss spectroscopy with comparisons to theiry10.1103/PhysRevB.26.614 ↗
38. Sayers · 2017
39. Barrier oxide chemistry and hydrogen pick-up mechanisms in zirconium alloys10.1016/j.corsci.2015.11.002 ↗
40. Atom probe tomography study of alloying element distributions in Zr alloys and their oxides
41. Microbeam X-ray absorption near-edge spectroscopy study of the oxidation of Fe and Nb in zirconium alloy oxide layers
42. The measurement of stress and phase fraction distributions in pre and post-transition Zircaloy oxides using nano-beam synchrotron X-ray diffraction
43. Transition electron microscopy characterisation of Zircaloy-4 and ZIRLO oxide layers
44. Direct observation of hydrogen and deuterium in oxide grain boundaries in corroded zirconiu alloys10.1016/j.corsci.2014.10.016 ↗
45. The role of metal plasticity in the growth of oxide on zircaloy-4