Hydrogen pickup measurements in zirconium alloys: Relation to oxidation kinetics
Source abstract
Abstract
Abstract The optimization of zirconium-based alloys used for nuclear fuel cladding aims to reduce hydrogen pickup during operation, and the associated cladding degradation. The present study focuses on precisely and accurately measuring hydrogen pickup fraction for a set of alloys to specifically investigate the effects of alloying elements, microstructure and corrosion kinetics on hydrogen uptake. To measure hydrogen concentrations in zirconium alloys two techniques have been used: a destructive technique, Vacuum Hot Extraction, and a non-destructive one, Cold Neutron Prompt Gamma Activation Analysis. The results of both techniques show that hydrogen pickup fraction varies significantly with exposure time and between alloys. A possible interpretation of the results is that hydrogen pickup results from the need to balance charge. That is, the pickup of hydrogen shows an inverse relationship to oxidation kinetics, indicating that, if transport of charged species is rate limiting, oxide transport properties such as oxide electronic conductivity play a key role in the hydrogen pickup mechanism. Alloying elements (either in solid solution or in precipitates) would therefore impact the hydrogen pickup fraction by affecting charge transport.
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 (49)
Show source-provided references
1. Motta · JOM · 2012 · 64 · 140310.1007/s11837-012-0479-x ↗
2. Corrosion of Zirconium Alloys in Nuclear Power Plants, IAEA-TECDOC-684, Vienna, 1993.
3. Waterside Corrosion of Zirconium Alloys in Nuclear Power Plants, IAEA-TECDOC-996, Vienna, 1998.
4. Cox · J. Nucl. Mater. · 2005 · 336 · 33110.1016/j.jnucmat.2004.09.029 ↗
5. Kass · J. Electrochem. Soc. · 1960 · 107 · 59410.1149/1.2427781 ↗
6. Klepfer · Corrosion · 1963 · 19 · 28510.5006/0010-9312-19.8.285 ↗
7. Berry · Corrosion · 1961 · 17 · 10910.5006/0010-9312-17.3.81 ↗
8. Cox · J. Nucl. Mater. · 1999 · 264 · 28310.1016/S0022-3115(98)00492-9 ↗
9. Kass · ASM Trans. Q. · 1962 · 55 · 77
10. Y. Hatano, M. Sugisaki, K. Kitano, M. Hayashi, Role of intermetallic precipitates in hydrogen transport through oxide films on zircaloy, in: Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, Philadelphia, 2000, pp. 901–917.10.1520/STP14333S ↗
11. Hillner · AEC Res. Develop. · 1964
12. Adamson · 2007
13. Cox · 1987
14. M. Harada, R. Wakamatsu, The effect of hydrogen on the transition behavior of the corrosion rate of zirconium alloys, in: Zirconium in the Nuclear Industry: 15th International Symposium, ASTM STP 1505, 2008, p. 384.10.1520/STP48146S ↗
15. Couet · J. Nucl. Mater. · 2012 · 425 · 21110.1016/j.jnucmat.2011.06.044 ↗
16. G.P. Sabol, R.J. Comstock, R.A. Weiner, P. Larouere, R.N. Stanutz, In-reactor corrosion performance of ZIRLO and Zircaloy-4, in: Zirconium in the Nuclear Industry: 10th International Symposium, ASTM STP 1245, Baltimore, 1994, pp. 724–744.10.1520/STP15217S ↗
17. A.T. Motta, M.J. Gomes Da Silva, A. Yilmazbayhan, R.J. Comstock, Z. Cai, B. Lai, Microstructural characterization of oxides formed on model Zr alloys using synchrotron radiation, in: Zirconium in the Nuclear Industry: 15th International Symposium, ASTM STP 1505, 2009, p. 486.10.1520/STP48151S ↗
18. 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 International, West Conshohocken, PA, 2011.
19. Methods of Chemical Analysis of Zirconium and Zirconium Alloys (Silicon, Hydrogen, and Copper), ASTM E146-83.
20. H. Wiese, Fractionated Determination of Hydrogen in Corroded Zirconium Alloys, PhD Thesis, Paul Scherrer Institute, Villigen, 1999.
21. Lindstrom · Biol. Trace Elem. Res. · 1994 · 43–45 · 59710.1007/BF02917362 ↗
22. Cox · 1965
23. Yilmazbayhan · J. Nucl. Mater. · 2004 · 324 · 610.1016/j.jnucmat.2003.08.038 ↗
24. Porte · J. Electrochem. Soc. · 1960 · 107 · 50610.1149/1.2427733 ↗
25. Hauffe · 1965
26. Fromhold · 1975
27. Bryner · J. Nucl. Mater. · 1979 · 82 · 8410.1016/0022-3115(79)90042-4 ↗
28. T. Murai, K. Isobe, Y. Takizawa, Y. Mae, Fundamental study on the corrosion mechanism of Zr–0.2Fe, Zr–0.2Cr and Zr–0.1Fe–0.2Cr alloys, in: Zirconium in the Nuclear Industry: 12th International Symposium, ASTM STP 1354, 2000, pp. 623–640.10.1520/STP14320S ↗
29. Y. Broy, F. Garzarolli, A. Seibold, L.F. Van Swam, Influence of transition elements Fe, Cr, and V on long-time corrosion in PWRs, in: Zirconium in the Nuclear Industry: 12th International Symposium, ASTM STP 1354, 2000, pp. 609–622.10.1520/STP14319S ↗
30. Kiselev · 1963
31. Choo · J. Nucl. Mater. · 1995 · 226 · 910.1016/0022-3115(95)00115-8 ↗
32. P. Bossis, D. Pecheur, K. Hanifi, J. Thomazet, M. Blat, Comparison of the high burn-up corrosion on M5 and low tin Zircaloy-4, in: Zirconium in the Nuclear Industry: Fourteenth International Symposium, ASTM STP 1467, 2005, pp. 494–524.10.1520/STP37522S ↗
33. Abriata · Bull. Alloy Phase Diagrams · 1982 · 3 · 1710
34. A. Couet, A.T. Motta, B. De Gabory, Z. Cai, J. Nucl. Mater., in press.
35. Kofstad · 1972
36. K. Sakamoto, K. Une, M. Aomi, K. Hashizume, Oxidation behavior of niobium in oxide layers of zirconium–niobium alloys, in: Top Fuel 2012, Manchester, UK, 2012, 297-306.
37. Kim · J. Electroanal. Chem. · 2005 · 576 · 26910.1016/j.jelechem.2004.11.002 ↗
38. K. Baur, F. Garzarolli, H. Ruhmann, H.-J. Sell, Electrochemical examinations in 350°C water with respect to the mechanism of corrosion-hydrogen pickup, in: Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, 2000, pp. 836–852.10.1520/STP14330S ↗
39. N. Ramasubramanian, P. Billot, S. Yagnik, Hydrogen evolution and pickup during the corrosion of zirconium alloys: a critical evaluation of the solid state and porous oxide electrochemistry, in: Zirconium in the Nuclear Industry: Thirteenth International Symposium, ASTM STP 1423, Philadelphia, USA, 2002, pp. 222–244.10.1520/STP11391S ↗
40. Schefold · J. Electrochem. Soc. · 2003 · 150 · B45110.1149/1.1602079 ↗
41. High temperature corrosion of Zircaloy-4
42. Pêcheur · J. Nucl. Mater. · 1992 · 189 · 31810.1016/0022-3115(92)90385-X ↗
43. A. Couet, A.T. Motta, R.J. Comstock, Effect of alloying elements on hydrogen pick-up in zirconium alloys, in: 17th International Symposium on Zirconium in the Nuclear Industry, ASTM STP 1543, Hyderabad, India, 2013.
44. Hudson · Scripta Mater. · 2009 · 61 · 41110.1016/j.scriptamat.2009.04.032 ↗
45. Proff · J. Nucl. Mater. · 2013 · 432 · 22210.1016/j.jnucmat.2012.06.026 ↗
46. Tupin · J. Nucl. Mater. · 2003 · 317 · 13010.1016/S0022-3115(02)01704-X ↗
47. H.-J. Beie, A. Mitwalsky, F. Garzarolli, H. Ruhmann, H.J. Sell, Examinations of the corrosion mechanism of zirconium alloys, in: Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245, Philadelphia, PA, 1994, pp. 615–643.10.1520/STP15212S ↗
48. B. Cox, Assessment of in-reactor corrosion models and data for Zircaloys in water, in: 2nd Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems–Water Reactors, Monterey, CA, USA, 1985, pp. 219–226.
49. G.P. Sabol, G.R. Kilp, M.G. Balfour, E. Roberts, Development of a cladding alloy for high burnup, in: Zirconium in the Nuclear Industry: 8th International Symposium, ASTM STP 1023, San Diego, 1989, pp. 227–244.10.1520/STP18868S ↗