journal article·2018-06Open access

Chemical and microstructural characterization of a 9 cycle Zircaloy-2 cladding using EPMA and FIB tomography

A. Baris, R. Restani, R. Grabherr, Y.-L. Chiu, H.E. Evans, K. Ammon, M. Limbäck, S. Abolhassani

Abstract

Abstract A high burn-up Zircaloy-2 cladding is characterised in order to correlate its microstructure and composition to the change of oxidation and hydrogen uptake behaviour during long term service in the reactor. After 9 cycle of service, the chemical analysis of the cladding segment shows that most secondary phase particles (SPPs) have dissolved into the matrix. Fe and Ni are distributed homogenously in the metal matrix. Cr-containing clusters, remnants of the original Zr(Fe, Cr)2 type precipitates, are still present. Hydrides are observed abundantly in the metal side close to the metal-oxide interface. These hydrides have lower Fe and Ni concentration than that in the metal matrix. The three-dimensional (3D) reconstruction of the oxide and the metal-oxide interface obtained by Focused Ion Beam (FIB) tomography shows how the oxide microstructure has evolved with the number of cycles. The composition and microstructural changes in the oxide and the metal can be correlated to the oxidation kinetics and the H-uptake. It is observed that there is an increase in the oxidation kinetics and in the H-uptake between the third and the fifth cycles, as well as during the last two cycles. At the same time the volume fraction of cracks in the oxide significantly increased. Many fine cracks and pores exist in the oxide formed in the last cycle. Furthermore, the EPMA results confirm that this oxide formed at the last cycle reflects the composition of the metal at the metal-oxide interface after the long residence time in the reactor.
Source: openaire · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Fusion materials and technologies

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

References (47)

Show source-provided references
1. Rickover · 1975
2. Cox · 1998
3. Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys10.1016/j.jnucmat.2004.09.029 ↗
4. The precipitation of zirconium hydride in zirconium and Zircaloy-210.1016/0022-3115(72)90021-9 ↗
5. Effects of thermomechanical processing on in-reactor corrosion and post irradiation mechanical properties of Zircaloy-2
6. Optimization of Zry-2 for high burnups
7. Effects of secondary phase particle dissolution on the in-reactor performance of BWR cladding
8. Corrosion of zirconium alloys used for nuclear fuel cladding10.1146/annurev-matsci-070214-020951 ↗
9. Corrosion and hydrogen uptake in zirconium claddings irradiated in light water reactors
10. Observation of crack microstructure in oxides and its correlation to oxidation and hydrogen-uptake by 3D FIB tomography – case of Zr-ZrO2 in reactor
11. Kofstad · 1988
12. Hydrogen pickup measurements in zirconium alloys: relation to oxidation kinetics10.1016/j.jnucmat.2014.03.001 ↗
13. A mechanism for the hydrogen uptake process in zirconium alloys10.1016/S0022-3115(98)00492-9 ↗
14. Hydrogen diffusion process in the oxides formed on zirconium alloys during corrosion in pressurized water reactor conditions10.1016/j.corsci.2016.10.027 ↗
15. ZIRLO™ - an alloy development success
16. Amorphous intermetallics in neutron irradiated Zircaloys after high fluences10.1016/0022-3115(85)90086-8 ↗
17. Recent observation on the evolution of the secondary phase particles in Zircaloy-2 under irradiation in a BWR up to a high burn-up
18. Anodic protection provided by precipitates in aqueous corrosion of Zircaloy
19. Examination of the chemical composition of irradiated zirconium based fuel claddings at the metal/oxide interface by TEM10.1016/j.jnucmat.2009.10.060 ↗
20. TEM examinations of the metal-oxide interface of zirconium based alloys irradiated in a pressurized water reactor
21. Microstructure and growth mechanism of oxide layers formed on Zr alloys studied with micro-beam synchrotron radiation
22. EELS and atom probe tomography study of the evolution of the metal/oxide interface during zirconium alloy oxidation10.1016/j.jnucmat.2015.03.043 ↗
23. Barrier oxide chemistry and hydrogen pick-up mechanisms in zirconium alloys10.1016/j.corsci.2015.11.002 ↗
24. Oxygen vacancy formation, mobility, and hydrogen pick-up during oxidation of zirconium by water10.1007/s11085-016-9695-z ↗
25. Focussed 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 ↗
26. Characterizing environmental degradation in PWRs by 3D FIB sequential sectioning
27. 3D analysis of crack morphologies in silicate glass using FIB tomography10.1016/j.jeurceramsoc.2008.05.042 ↗
28. Influence of cryogenic drying conditions on hierarchical porous structure of aluminum oxide systems10.1016/j.micromeso.2015.06.018 ↗
29. Three-dimensional analysis of porous BaTiO3 ceramics using FIB nanotomography10.1111/j.0022-2720.2004.01397.x ↗
30. Pore-scale simulation of transport properties of carbonate rocks using FIB-SEM 3D microstructure: implications for field scale solute transport simulations10.1016/j.jngse.2017.02.044 ↗
31. Growth directions of precipitates in the Al-Si-Mg-Hf alloy using combined EBSD and FIB 3D-reconstruction techniques10.1017/S1431927615000549 ↗
32. Review of FIB-tomography
33. The effect of liner component iron content on cladding corrosion, hydriding, and PCI resistance10.1520/JAI12444 ↗
34. Fuel performance beyond design - exploring the limits
35. Mehrer · 1990 · 26
36. Redistribution of alloying elements in Zircaloy-2 after in-reactor exposure10.1016/j.jnucmat.2014.07.072 ↗
37. Diffusion of oxygen in growing zirconia films10.1016/0022-3115(68)90058-5 ↗
38. Metal and oxygen mobilities during Zircaloy-4 oxidation at high temperature10.1016/S0022-3115(99)00036-7 ↗
39. In situ study of the oxidation of Zircaloy-4 by ESEM10.1016/S0022-3115(03)00201-0 ↗
40. In situ oxidation of zirconium binary alloys by environmental SEM and analysis by AFM, FIB, and TEM10.1016/j.jnucmat.2010.05.012 ↗
41. FEI · 2017
42. Synchrotron X-ray diffraction investigations on strains in the oxide layer of an irradiated Zircaloy fuel cladding10.1016/j.jnucmat.2017.03.010 ↗
43. Origin and effect of lateral cracks in oxide scales formed on zirconium alloys10.1016/j.jnucmat.2012.06.039 ↗
44. Terminal solid solubility of hydrogen in unalloyed zirconium by differential scanning calorimetry10.1080/18811248.2004.9715569 ↗
45. Zr2FeHx system hydrided at low temperatures: structural aspects by Mössbauer and x-ray diffraction studies10.1016/0925-8388(92)90280-M ↗
46. Phase separation in hydrides of Zr2Ni10.1007/BF02396126 ↗
47. Contribution to a better understanding of the detrimental role of hydrogen on the corrosion rate of Zircaloy-4 cladding materials