Correlation between microstructure and corrosion behavior of Zr–Nb binary alloy
Source abstract
Abstract
To investigate the correlation between microstructure and corrosion characteristics of Zr–Nb alloy, the microstructural observation and corrosion test with the change of cooling rate from beta temperature and the variation of Nb content were performed. The oxide characterization was also carried out by synchrotron XRD and TEM. When the Nb is contained less than solid solution limit (0.6 wt%) in Zr matrix, the difference of corrosion rate was not observed in spite of showing the significant changes of microstructures with cooling rate. While, when the Nb content in the alloy is more than 0.6 wt%, the corrosion properties were deteriorated with increasing the supersaturated Nb concentration in matrix and increasing the area fraction of bZr. Also it was observed that the supersaturated Nb in matrix was more effective to decrease the corrosion resistance than the bZr phase in the same Nb containing alloy, while the equilibrium Nb concentration below solubility limit in the matrix played an important role to enhance the corrosion resistance. During the corrosion testing in steam at 400 C, the formation of bNb phase in water-quenched specimen would result in the reduction of Nb concentration in matrix. Thus, the corrosion resistance is enhanced with the formation of bNb phase. It is suggested from this study that the equilibrium Nb concentration below solubility limit in a matrix would be a more dominant factor in the enhancement of corrosion resistance than b phase (bNb or bZr), supersaturated Nb, precipitate, and internal microstructure such as twin, dislocation and plate. 2002 Elsevier Science B.V. All rights reserved.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Titanium Alloys Microstructure and Properties · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (23)
Show source-provided references
1. Zirconium in the Nuclear Industry
2. K. Yamate, A. Oe, M. Hayashi, T. Okamoto, H. Anada, S. Hagi, in: Proceedings of the 1997 International Topical Meeting on LWR Fuel Performance, Portland, OR, 2–6 March, 1997, p. 318
3. J.P. Mardon, G. Garner, P. Beslu, D. Charquer, J. Senevat, in: Proceedings of the 1997 International Topical Meeting on LWR Fuel Performance, Portland, OR, 2–6 March, 1997, p. 405
4. V.F. Urbanic, R.W. Gilbert, in: IAEA Technical Committee Meeting on Fundamental Aspects of Corrosion of Zr-based Alloys for Water Reactor Environments, Portland, OR, 11–15 September, 1989, p. 262
5. Zirconium in the Nuclear Industry
6. Kim · J. Kor. Inst. Met. Mater. · 1999 · 37 · 584
7. Jeong · Kor. J. Mater. Res. · 1996 · 6 · 585
8. Zirconium in the Nuclear Industry
9. Banerjee · J. Nucl. Mater. · 1976 · 62 · 22910.1016/0022-3115(76)90019-2 ↗
10. Aldridge · J. Nucl. Mater. · 1972 · 42 · 3210.1016/0022-3115(72)90004-9 ↗
11. Javanovic · J. Nucl. Mater. · 1997 · 244 · 14110.1016/S0022-3115(96)00732-5 ↗
12. Nishiyama · 1978
13. Hunt · J. Nucl. Mater. · 1971 · 38 · 1710.1016/0022-3115(71)90003-1 ↗
14. Porter · 1992
15. Choo · J. Nucl. Mater. · 1994 · 209 · 22610.1016/0022-3115(94)90256-9 ↗
16. ASTM Spec. Tech. Publ. · 1977 · 633 · 211
17. Zirconium in the Nuclear Industry
18. Zirconium in the Nuclear Industry
19. Zirconium in the Nuclear Industry
20. Zirconium in the Nuclear Industry
21. Zirconium in the Nuclear Industry
22. Sabol · J. Nucl. Mater. · 1970 · 34 · 14210.1016/0022-3115(70)90114-5 ↗
23. Williams · J. Nucl. Mater. · 1966 · 18 · 16110.1016/0022-3115(66)90078-X ↗