Effect of ion irradiation of the metal matrix on the oxidation rate of Zircaloy-4
Source abstract
Abstract
Abstract The oxidation kinetics acceleration observed in Zircaloy-4 cladding in Pressurized Water Reactor could be partially due to metal irradiation damage occuring in-pile. To check this assumption, several ion irradiation tests of the Zircaloy-4 metal matrix were performed to reproduce the evolution of the metallurgical state in reactor. This study showed that the amorphization process of the intermetallic precipitates (SPPs) does not change significantly the oxidation rate of Zircaloy-4. Implantation of iron in the matrix to simulate iron dissolution from the SPPs has no real impact on the corrosion kinetics. However proton irradiations at 350 °C producing dislocation loops resulted in a significant increase in the oxidation rate.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear materials and radiation effects
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (46)
Show source-provided references
1. Performance of alloy M5™ cladding and structure
2. Verlet · Corros. Sci. · 2015 · 98 · 32710.1016/j.corsci.2015.05.045 ↗
3. In PWR comprehensive study of high burn-up corrosion and growth behavior of M5 and recrystallized low-tin zircaloy-4
4. A new model to predict the oxidation kinectics of zirconium alloys in a Pressurized Water Reactor
5. Detrimental role of hydrogen on the corrosion rate of zirconium alloys
6. Contribution to a better understanding of the detrimental role of hydrogen on the corrosion rate of Zircaloy-4 cladding materials
7. Kido · 1993 · 449
8. Tupin · Corros. Sci. · 2015 · 98 · 47810.1016/j.corsci.2015.05.058 ↗
9. Comparison of the high burn-up corrosion on M5 and low tin Zircaloy-4
10. Corrosion behavior of zircaloy-4 cladding with varying tin content in high-temperature pressurized water reactors
11. Comparison of the long-time corrosion behavior of certain Zr alloys in PWR, BWR, and laboratory tests
12. Microstructure evolutions and iron redistribution in zircaloy oxide layers: comparative effects of neutron irradiation flux and irradiation damages
13. Iltis · J. Nucl. Mater. · 1995 · 224 · 12110.1016/0022-3115(95)00069-0 ↗
14. Role of the second-phase particles in zirconium binary alloys
15. Jin · Annals. Nucl. Energy · 2015 · 75 · 30910.1016/j.anucene.2014.08.042 ↗
16. Dayal · J. Nucl. Mater. · 2013 · 438 · 10810.1016/j.jnucmat.2013.02.078 ↗
17. Gilbon · 2008 · 38
18. Understanding of corrosion mechanisms of zirconium alloys after irradiation: effect of ion irradiation of the oxide layers on the corrosion rate
19. Northwood · Atomic Energy Rev. · 1977 · 15 · 547
20. Northwood · J. Nucl. Mater. · 1979 · 79 · 37910.1016/0022-3115(79)90103-X ↗
21. Griffiths · J. Nucl. Mater. · 1988 · 159 · 19010.1016/0022-3115(88)90093-1 ↗
22. Griffiths · J. Nucl. Mater. · 1987 · 150 · 15910.1016/0022-3115(87)90071-7 ↗
23. Evolution of microstructure in zirconium alloys during irradiation
24. Irradiation creep and growth behavior, and microstructural evolution of advanced Zr-base alloys
25. Amorphization of precipitates in Zircaloy under neutron and charged-particles irradiation
26. Arevalo · J. Nucl. Mater. · 2007 · 362 · 29310.1016/j.jnucmat.2007.01.079 ↗
27. Onimus · 2012
28. Fidleris · J. Nucl. Mater. · 1988 · 159 · 2210.1016/0022-3115(88)90083-9 ↗
29. Dali · J. Nucl. Mater. · 2012 · 426 · 14810.1016/j.jnucmat.2012.03.030 ↗
30. Role of the second-phase particles in zirconium binary alloys
31. Zu · Philos. Mag. · 2005 · 85 · 64910.1080/14786430412331320017 ↗
32. Microstructural evolution of M5™7 alloy irradiated in PWRs up to high fluences –comparison with other Zr-based alloys
33. Amorphization of precipitates in Zircaloy under neutron and charged-particles irradiation
34. Pêcheur · 1993
35. Ni · Scripta Mater. · 2010 · 62 · 56410.1016/j.scriptamat.2009.12.043 ↗
36. Yan · Nucl. Eng. Technol. · 2015 · 47 · 32310.1016/j.net.2014.12.015 ↗
37. Idrees · J. Nucl. Mater. · 2013 · 433 · 9510.1016/j.jnucmat.2012.09.014 ↗
38. Ni · Corr. Sci. · 2011 · 53 · 407310.1016/j.corsci.2011.08.013 ↗
39. Parise · J. Nucl. Mater. · 1998 · 256 · 3510.1016/S0022-3115(98)00045-2 ↗
40. Bossis · Mater. Sci. Forum · 2001 · 369–372 · 25510.4028/www.scientific.net/MSF.369-372.255 ↗
41. Platt · J. Nucl. Mater. · 2015 · 464 · 31310.1016/j.jnucmat.2015.05.002 ↗
42. Cournil · J. Chim. Phys. · 1977 · 74 · 54510.1051/jcp/1977740545 ↗
43. Tupin · J. Nucl. Mater. · 2003 · 317 · 13010.1016/S0022-3115(02)01704-X ↗
44. Zumpicchiat · Corros. Sci. · 2015 · 100 · 20910.1016/j.corsci.2015.07.024 ↗
45. Microstructure evolution in ion-irradiated oxidized Zircaloy-4 studied with synchrotron radiation micro-diffraction and transmission electron microscopy
46. Influence of the hydride precipitation on the corrosion kinetics of Zircaloy-4: Effect of the nanostructure and grain boundaries properties of zirconium oxide layer on the oxygen diffusion flux