journal article·2015-06Open access

The recovery of irradiation damage for Zircaloy-2 and Zircaloy-4 following low dose neutron irradiation at nominally 358 °C

B.V. Cockeram, K.J. Leonard, T.S. Byun, L.L. Snead, J.L. Hollenbeck

Abstract

Abstract The recovery of irradiation damage in wrought Zircaloy-2 and Zircaloy-4 was determined following a series of post-irradiation anneals at temperatures ranging from 343 °C to 510 °C and for time periods ranging from 1-h to 500 h. The materials had been irradiated at nominally 358 °C in the High Flux Isotope Reactor (HFIR) at neutron fluences of nominally 3 × 1025 n/m2 (E > 1 MeV). Irradiation at nominally 358 °C resulted in a coarser distribution of 〈a〉 loops that result in a 25–45% lower irradiation hardening than reported in the literature for irradiations at 260–326 °C. The irradiation hardening and recovery were determined using tensile testing at room-temperature. Post-irradiation annealing at 343–427 °C was shown to result in an increase in irradiation hardening to values even higher than for the as-irradiated material in the first 1–10 h of annealing. This Radiation Anneal Hardening (RAH) was followed by a relatively slow recovery of the irradiation damage. Much faster recovery with no RAH was observed for post-irradiation annealing at temperatures of 454–510 °C. Irradiation at 358 °C was shown to result in different recovery kinetics than observed in the literature for irradiation at 260–326 °C. While the general trend described above is true for the four materials tested (alpha-annealed and beta-treated Zircaloy-2 and Zircaloy-4), notable and yet unexplained differences in RAH and in recovery are observed between the materials that might be a result of differing solute effects. Examinations of microstructure using Transmission Electron Microscopy were used to investigate the RAH and recovery mechanisms. Agreement between the measured and calculated irradiation hardening using a generalized Orowan hardening model to account for the observed loop structure was not as close for the post irradiation annealed condition as for the as-irradiated condition, which can likely be attributed to unaccounted for changes in the configuration of the 〈a〉 loops to dislocation lines, segregation of solutes to dislocation loops, and the potential for the formation of fine clusters of point defects or solutes during annealing.
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OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear materials and radiation effects

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References (71)

Show source-provided references
1. Ominus · 2012
2. R. Adamson, B. Cox, ZIRAT-10 Special Topics Report, Impact of Irradiation on Material Performance, ANT International, Sweden, October, 2005.
3. Kreyns · 1996 · 758
4. Cockeram · J. Nucl. Mater. · 2011 · 418 · 48
5. Cockeram · J. Nucl. Mater. · 2014 · 449 · 6910.1016/j.jnucmat.2014.03.004 ↗
6. Griffiths · J. Nucl. Mater. · 1988 · 159 · 19010.1016/0022-3115(88)90093-1 ↗
7. Griffiths · J. Nucl. Mater. · 1987 · 150 · 15910.1016/0022-3115(87)90071-7 ↗
8. Yang · J. Nucl. Mater. · 1986 · 138 · 18510.1016/0022-3115(86)90005-X ↗
9. Holt · J. Nucl. Mater. · 1970 · 35 · 32210.1016/0022-3115(70)90216-3 ↗
10. Churquet · 1988 · 405
11. Motta · 2002 · 59
12. Woo · J. Nucl. Mater. · 1979 · 87 · 13510.1016/0022-3115(79)90132-6 ↗
13. Griffiths · J. Nucl. Mater. · 1995 · 225 · 24510.1016/0022-3115(94)00687-3 ↗
14. Northwood · J. Nucl. Mater. · 1979 · 79 · 37910.1016/0022-3115(79)90103-X ↗
15. Hashimoto · Mater. Sci. Forum · 2007 · 561–565 · 176910.4028/www.scientific.net/MSF.561-565.1769 ↗
16. Kakiuchi · J. Nucl. Technol. · 2006 · 43 · 103110.1080/18811248.2006.9711192 ↗
17. Kelly · Philos. Mag. · 1973 · 28 · 41510.1080/14786437308217463 ↗
18. Howe · J. Nucl. Mater. · 1960 · 2 · 24810.1016/0022-3115(60)90059-3 ↗
19. R.B. Adamson, W.L. Bell, Effects of Neutron Irradiation and Oxygen Content on the Microstructure and Mechanical Properties of zircaloy: Microstructure and Mechanical Behavior of Materials, vol. I, X’ian, Republic of China, October 21–24, EMAS Warley, UK, 1985, pp. 237–246.
20. Ribis · J. ASTM Int. · 2008 · 510.1520/JAI101118 ↗
21. Carpenter · 1974 · 400
22. C.D. Williams, R.W. Gilbert, in: Proceedings of the IAEA Symposium, Vienna, vol. 1, 1969, p. 235.
23. Northwood · J. Nucl. Mater. · 1977 · 64 · 30810.1016/0022-3115(77)90084-8 ↗
24. C. Regnard et al., in: Proceeding of the 13th International Symposium on Zirconium in the Nuclear Industry, ASTM STP 1423, 2002, p. 384.10.1520/STP11398S ↗
25. Gilbert · J. Nucl. Mater. · 1979 · 84 · 13710.1016/0022-3115(79)90157-0 ↗
26. Carpenter · J. Nucl. Mater. · 1975 · 56 · 26010.1016/0022-3115(75)90041-0 ↗
27. Gulden · Philos. Mag. · 1966 · 14 · 108710.1080/14786436608244779 ↗
28. Kelly · Philos. Mag. · 1973 · 28 · 41510.1080/14786437308217463 ↗
29. Northwood · J. Nucl. Mater. · 1976 · 61 · 12310.1016/0022-3115(76)90076-3 ↗
30. Jostons · J. Nucl. Mater. · 1977 · 66 · 23610.1016/0022-3115(77)90113-1 ↗
31. Carpenter · J. Nucl. Mater. · 1981 · 96 · 21310.1016/0022-3115(81)90565-1 ↗
32. Hellio · J. Nucl. Mater. · 1988 · 159 · 36810.1016/0022-3115(88)90103-1 ↗
33. Griffiths · Philos. Mag. B · 1991 · 63 · 83510.1080/01418619108213917 ↗
34. Griffiths · J. Nucl. Mater. · 1993 · 205 · 22510.1016/0022-3115(93)90085-D ↗
35. Griffiths · J. Nucl. Mater. · 1990 · 170 · 29410.1016/0022-3115(90)90302-4 ↗
36. Ribis · J ASTM Int. · 2009 · 5 · 674
37. Ribis · J. Nucl. Mater. · 2010 · 403 · 13510.1016/j.jnucmat.2010.06.012 ↗
38. Griffiths · J. Nucl. Mater. · 1988 · 159 · 40510.1016/0022-3115(88)90107-9 ↗
39. A.L. Bement, J.C. Tobin, R.G. Hoagland, ASTM STP-380, June 1964.
40. A.L. Bement, Radiation Damage in Hexagonal Close-Packed Metals and Alloys, BNWL-SA-236, June 1, 1965.10.2172/4593064 ↗
41. Griffiths · 1989 · 658
42. Douglass · 1971
43. Higgy · J. Nucl. Mater. · 1972 · 44 · 21510.1016/0022-3115(72)90099-2 ↗
44. S.B. Wisner, G.H. Henderson, R.P. Tucker, R.B. Adamson, Mechanical Properties of Zircaloy Irradiated in the EBR-II, GEAP-25163-10, Appendix B, 1984.
45. Torimaru · J. Nucl. Mater. · 1996 · 238 · 16910.1016/S0022-3115(96)00451-5 ↗
46. Mahmood · 2000 · 139
47. Lustman · Nucleonics · 1961 · 19 · 58
48. D.G. Hardy, ASTM STP-484, June 1970.
49. Klepfer · 1960 · Vol. VIII
50. Wisner · Nucl. Eng. Des. · 1998 · 185 · 3310.1016/S0029-5493(98)00155-1 ↗
51. Morize · 1987 · 101
52. R.S. Ishimoto, T. Kubo, O. Kubota, Development of New Zirconium Alloys for High Burnup Fuel, in: Proceedings of TopFuel 2003, Wurzburg, Germany, 2003.
53. Onimus · J. Nucl. Mater. · 2004 · 328 · 16510.1016/j.jnucmat.2004.04.337 ↗
54. Standard Test Methods for Tension Testing of Metallic Materials, ASTM E8-01, American Society for Testing and Materials, Philadelphia, PA, 2001.
55. Bauer · Nucl. Technol. · 1978 · 41 · 35910.13182/NT78-A32120 ↗
56. Snowden · Radiat. Eff. · 1973 · 20 · 16910.1080/00337577308232280 ↗
57. Veevers · ASTM STP · 1969 · 458 · 194
58. Harbinson · J. Mater. · 1968 · 3 · 107
59. Meechan · Phys. Rev. · 1956 · 103 · 119310.1103/PhysRev.103.1193 ↗
60. Harvey · 1982 · 505
61. Pachur · Nucl. Technol. · 1982 · 59 · 46310.13182/NT82-A33004 ↗
62. Cockeram · J. Nucl. Mater. · 2005 · 336 · 29910.1016/j.jnucmat.2004.10.119 ↗
63. J. Philibert, Atom Movements, Diffusion, and Mass Transport, Les Editions de Physique, p. 191.
64. Merle · ASM STP · 1987 · 939 · 555
65. Dollins · J. Nucl. Mater. · 1975 · 59 · 6110.1016/0022-3115(76)90008-8 ↗
66. Cockeram · J. Nucl. Mater. · 2013 · 433 · 46010.1016/j.jnucmat.2012.10.006 ↗
67. Was · 2007
68. D.R. Olander, Fundamental Aspects of Nuclear Reactor Fuel Elements, Technical Information Center, US-DOE, ERDA, 1976.10.2172/7343826 ↗
69. Bajaj · Met. Trans. · 1976 · 7A · 35110.1007/BF02642830 ↗
70. M. Griffiths, Zirconium in the Nuclear Industry: Fifteenth International Symposium, ASTM STP 1505, J. ASTM International, vol. 5, 2009, pp. 19–26.
71. Wechsler · 1973