Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Effects of ion irradiation on microstructure and properties of zirconium alloys-A review

  • Yan, Chunguang (State Key Laboratory for Advanced Metals and Materials, University of Science and Technology Beijing) ;
  • Wang, Rongshan (Life Management Technology Center, Suzhou Nuclear Power Research Institute) ;
  • Wang, Yanli (State Key Laboratory for Advanced Metals and Materials, University of Science and Technology Beijing) ;
  • Wang, Xitao (State Key Laboratory for Advanced Metals and Materials, University of Science and Technology Beijing) ;
  • Bai, Guanghai (Life Management Technology Center, Suzhou Nuclear Power Research Institute)
  • Received : 2014.07.18
  • Accepted : 2014.12.10
  • Published : 2015.04.25
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Abstract

Zirconium alloys are widely used in nuclear reactors as structural materials. During the operation, they are exposed to fast neutrons. Ion irradiation is used to simulate the damage introduced by neutron irradiation. In this article, we briefly review the neutron irradiation damage of zirconium alloys, then summarize the effect of ion irradiation on microstructural evolution, mechanical and corrosion properties, and their relationships. The microstructure components consist of dislocation loops, second phase precipitates, and gas bubbles. The microstructure parameters are also included such as domain size and microstrain determined by X-ray diffraction and the S-parameter determined by positron annihilation. Understanding the relationships of microstructure and properties is necessary for developing new advanced materials with higher irradiation tolerance.

Keywords

References

  1. J.H. Kim, M.H. Lee, B.K. Choi, Y.H. Jeong, Failure behavior of Zircaloy-4 cladding after oxidation and water quench, J. Nucl. Mater. 362 (2007) 36-45. https://doi.org/10.1016/j.jnucmat.2006.10.026
  2. S.I. Choi, J.H. Kim, Radiation-induced dislocation and growth behavior of zirconium and zirconium alloys - a review, Nucl. Eng. Technol. 45 (2013) 385-392. https://doi.org/10.5516/NET.07.2013.035
  3. M.J. Fluss, P. Hosemann, J. Marian, Charged-particle Irradiation for Neutron Radiation Damage Studies, Characterization of Materials, John Wiley & Sons, Inc., Hoboken, NY, 2002.
  4. G.S. Was, Fundamentals of Radiation Materials Science: Metals and Alloys, Springer, Verlag Berlin Heidelberg, 2007.
  5. G.S. Was, Materials degradation in fission reactors: Lessons learned of relevance to fusion reactor systems, J. Nucl. Mater. 367 (2007) 11-20.
  6. R. Adamson, F. Garzarolli, C. Patterson, In-reactor Creep of Zirconium Alloys, Advance Nuclear Technology International, Sweden, 2009.
  7. X.M. Bai, A.F. Voter, R.G. Hoagland, M. Nastasi, B.P. Uberuaga, Efficient annealing of radiation damage near grain boundaries via interstitial emission, Science 327 (2010) 1631-1634. https://doi.org/10.1126/science.1183723
  8. H. Wiedersich, P. Okamoto, N.Q. Lam, A theory of radiationinduced segregation in concentrated alloys, J. Nucl. Mater. 83 (1979) 98-108. https://doi.org/10.1016/0022-3115(79)90596-8
  9. Y. Etoh, S. Shimada, Irradiation-induced dissolution of precipitates in Zircaloy-2, J. Nucl. Sci. Technol. 29 (1992) 358-366. https://doi.org/10.1080/18811248.1992.9731535
  10. M. Griffiths, A review of microstructure evolution in zirconium alloys during irradiation, J. Nucl. Mater. 159 (1988) 190-218. https://doi.org/10.1016/0022-3115(88)90093-1
  11. M. Griffiths, J.F. Mecke, J.E. Winegar, Evolution of microstructure in zirconium alloys during irradiation, Zirconium in the Nuclear Industry: Eleventh International Symposium, STP1295 (1996) 580-602.
  12. M. Griffiths, R.W. Gilbert, V. Fidleris, R.P. Tucker, R.B. Adamson, Neutron damage in zirconium alloys irradiated at 644 to 710 K, J. Nucl. Mater. 150 (1987) 159-168. https://doi.org/10.1016/0022-3115(87)90071-7
  13. Y. de Carlan, D. Gilbon, M. Griffiths, D. Gibon, C. Lemaignan, Influence of iron in the nucleation of component dislocation loops in irradiated zircaloy-4, Zirconium in the Nuclear Industry: Eleventh International Symposium, STP1295 (1996) 638-653.
  14. R. Holt, A. Causey, M. Griffiths, E. HO, High-fluence irradiation growth of cold-worked Zr-2.5Nb, Zirconium in the Nuclear Industry: Twelfth International Symposium, STP1354 (2000) 86-104.
  15. G.P. Sabol, G.R. Kilp, M.G. Balfour, E. Roberts, Development of a cladding alloy for high burnup, Zirconium in the Nuclear Industry: Eighth International Symposium, STP1023 (1989) 227-244.
  16. V.N. Shishov, M.M. Peregud, A.V. Nikulina, V.F. Kon'kov, V.V. Novikov, V.A. Markelov, T.N. Khokhunova, G.P. Kobylyansky, A.E. Novoselov, Z.E. Ostrovsky, A.V. Obukhov, Structure-phase state, corrosion and irradiation properties of Zr-Nb-Fe-Sn system alloys, Zirconium in the Nuclear Industry: 15th International Symposium, STP1505 (2008) 724-743.
  17. J.P. Mardon, D. Charquet, J. Senevat, M. Griffiths, B.D. Warr, A. Stasser, J.R. Theaker, H. Rosenbaum, B. Cheng, Influence of composition and fabrication process on out-of-pile and in-pile properties of M5 alloy, Zirconium in the Nuclear Industry: Twelfth International Symposium. STP1354 (2000) 505-524.
  18. Y.H. Jeong, S.Y. Park, M.H. Lee, B.K. Choi, J.H. Beak, J.Y. Park, J.H. Kim, H.G. Kim, Out-of-pile and in-pile performance of advanced zirconium alloys (HANA) for high burn-up fuel, J. Nucl. Sci. Technol. 43 (2006) 977-983. https://doi.org/10.1080/18811248.2006.9711185
  19. A.T. Motta, F. Lefebvre, C. Lemaignan, Amorphization of precipitates in Zircaloy under neutron and chargedparticle irradiation, Zirconium in the Nuclear Industry: Ninth International Symposium. STP1132 (1991) 718-739.
  20. M. Griffiths, R.W. Gilbert, G.J.C. Carpenter, Phase instability, decomposition and redistribution of intermetallic precipitates in Zircaloy-2 and-4 during neutron irradiation, J. Nucl. Mater. 150 (1987) 53-66. https://doi.org/10.1016/0022-3115(87)90093-6
  21. Y. Etoh, S. Shimada, Neutron irradiation effects on intermetallic precipitates in Zircaloy as a function of fluence, J. Nucl. Mater. 200 (1993) 59-69. https://doi.org/10.1016/0022-3115(93)90009-N
  22. Y. Etoh, Microstructure and corrosion resistance of irradiated fuel cladding tubes, J. Nucl. Sci. Technol. 29 (1992) 589-597. https://doi.org/10.1080/18811248.1992.9731569
  23. H.R. Higgy, F.H. Hammad, Effect of neutron irradiation on the tensile properties of zircaloy-2 and zircaloy-4, J. Nucl. Mater. 44 (1972) 215-227. https://doi.org/10.1016/0022-3115(72)90099-2
  24. T. Onchi, H. Kayano, Y. Higashiguchi, Effect of neutron irradiation on deformation behavior of zirconium, J. Nucl. Sci. Technol. 14 (1997) 359-369.
  25. D.O. Northwood, R.A. Herring, Irradiation growth of zirconium alloy nuclear reactor structural components, J. Mater. Energy Syst. 4 (1983) 195-216. https://doi.org/10.1007/BF02833441
  26. V. Shishov, M. Peregud, A. Nikulina, P. Shebaldov, A. Tselischev, A. Novoselov, G. Kobylyansky, Z. Ostrovsky, V. Shamardin, Influence of zirconium alloy chemical composition on microstructure formation and irradiation induced growth, Zirconium in the Nuclear Industry: Thirteenth International Symposium, STP1423 (2002) 758-779.
  27. M. Nakatsuka, M. Nagai, Reduction of plastic anisotropy of zircaloy cladding by neutron irradiation (II), J. Nucl. Sci. Technol. 24 (1987) 906-914. https://doi.org/10.1080/18811248.1987.9733520
  28. M. Nakatsuka, M. Nagai, Reduction of plastic anisotropy of zircaloy cladding by neutron irradiation (I), J. Nucl. Sci. Technol. 24 (1987) 832-838. https://doi.org/10.1080/18811248.1987.9735886
  29. D. Lee, E.F. Koch, Irradiation damage in Zircaloy-2 produced by high-dose ion bombardment, J. Nucl. Mater. 50 (1974) 162-174. https://doi.org/10.1016/0022-3115(74)90153-6
  30. F. Onimus, J.L. Bꠑechade, Radiation Effects in Zirconium Alloys, Comprehensive Nuclear Mater, Elsevier, Oxford, 2012.
  31. C. Hellio, C.H. de Novion, L. Boulanger, Influence of alloying elements on the dislocation loops created by $Zr^+$ ion or by electron irradiation in a-zirconium, J. Nucl. Mater. 159 (1988) 368-378. https://doi.org/10.1016/0022-3115(88)90103-1
  32. R.M. Hengstler-Eger, P. Baldo, L. Beck, J. Dorner, K. Ertl, P.B. Hoffmann, C. Hugenschmidt, M.A. Kirk, W. Petry, P. Pikart, A. Rempel, Heavy ion irradiation induced dislocation loops in AREVA's $M5^{(R)}$ alloy, J. Nucl. Mater. 423 (2012) 170-182. https://doi.org/10.1016/j.jnucmat.2012.01.002
  33. Y. Idrees, Z. Yao, M.A. Kirk, M.R. Daymond, In situ study of defect accumulation in zirconium under heavy ion irradiation, J. Nucl. Mater. 433 (2013) 95-107. https://doi.org/10.1016/j.jnucmat.2012.09.014
  34. M. Griffiths, R.W. Gilbert, The formation of c-component defects in zirconium alloys during neutron irradiation, J. Nucl. Mater. 150 (1987) 169-181. https://doi.org/10.1016/0022-3115(87)90072-9
  35. H. Zou, G.M. Hood, J.A. Roy, R.H. Packwood, Irradiation effects on Fe distributions in Zircaloy-2 and Zr-2.5Nb, MRS Proc. 373 (1994) 201-206. https://doi.org/10.1557/PROC-373-201
  36. H. Zou, G.M. Hood, J.A. Roy, R.H. Packwood, Irradiationdriven solute redistribution in Zr alloys, J. Nucl. Mater. 245 (1997) 248-252. https://doi.org/10.1016/S0022-3115(96)00711-8
  37. P.R. Okamoto, L.E. Rehn, Radiation-induced segregation in binary and ternary alloys, J. Nucl. Mater. 83 (1997) 2-23.
  38. A. Takeuchi, A. Inoue, Calculations of mixing enthalpy and mismatch entropy for ternary amorphous alloys, Mater. Trans. 41 (2000) 1372-1378. https://doi.org/10.2320/matertrans1989.41.1372
  39. Y. Idrees, Z. Yao, M. Sattari, M.A. Kirk, M.R. Daymond, "Irradiation induced microstructural changes in Zr-Excel alloy, J. Nucl. Mater. 441 (2013) 138-151. https://doi.org/10.1016/j.jnucmat.2013.05.036
  40. S. Yamada, T. Kameyama, Observation of c-component dislocation structures formed in pure Zr and Zr-base alloy by self-ion accelerator irradiation, J. Nucl. Mater. 422 (2012) 167-172. https://doi.org/10.1016/j.jnucmat.2011.12.035
  41. L. Tournadre, F. Onimus, J.L. Bꠑechade, D. Gilbon, J.M. Clouꠑe, J.P. Mardon, X. Feaugas, O. Toader, C. Bachelet, Experimental study of the nucleation and growth of c-component loops under charged particle irradiations of recrystallized Zircaloy- 4, J. Nucl. Mater. 425 (2012) 76-82. https://doi.org/10.1016/j.jnucmat.2011.11.061
  42. J.J. Kai, W.I. Huang, H.Y. Chou, The microstructural evolution of zircaloy-4 subjected to proton irradiation, J. Nucl. Mater. 170 (1990) 193-209. https://doi.org/10.1016/0022-3115(90)90412-G
  43. F. Lefebvre, C. Lemaignan, Heavy ion-induced amorphlsation of $Zr(Fe,Cr)_2$ precipitates in Zircaloy-4, J. Nucl. Mater. 165 (1989) 122-127. https://doi.org/10.1016/0022-3115(89)90240-7
  44. A.T. Motta, D.R. Olander, Irradiation-induced Changes in Zircaloy Intermetallics, Electric Power Research Inst., Palo Alto, 1990.
  45. F. Lefebvre, C. Lemaignan, Analysis with heavy ions of the amorphisation under irradiation of $Zr(Fe,Cr)_2$ precipitates in zircaloy-4, J. Nucl. Mater. 171 (1990) 223-229. https://doi.org/10.1016/0022-3115(90)90369-X
  46. X.T. Zu, K. Sun, M. Atzmon, L.M. Wang, L.P. You, F.R. Wan, J.T. Busby, G.S. Was, R.B. Adamson, Effect of proton and Ne irradiation on the microstructure of Zircaloy 4, Philos. Mag. 85 (2005) 649-659. https://doi.org/10.1080/14786430412331320017
  47. H.H. Shen, S.M. Peng, X. Xiang, F.N. Naab, K. Sun, X.T. Zu, Proton irradiation effects on the precipitate in a Zr-1.6Sn- 0.6Nb-0.2Fe-0.1Cr alloy, J. Nucl. Mater. 452 (2014) 335-342. https://doi.org/10.1016/j.jnucmat.2014.05.042
  48. H.H. Shen, J.M. Zhang, S.M. Peng, X. Xiang, K. Sun, X.T. Zu, In situ TEM investigation of amorphization and recrystallization of $Zr(Fe,Cr,Nb)_2$ precipitates under Ne ion irradiation, Vacuum 110 (2014) 24-29. https://doi.org/10.1016/j.vacuum.2014.08.002
  49. M.L. Swanson, J.R. Parsons, C.W. Hoelke, Damaged regions in neutron-irradiated and ion-bombarded Ge and Si, Radiat. Eff. 9 (1971) 249-256. https://doi.org/10.1080/00337577108231056
  50. L.M. Howe, D. Phillips, H. Zou, J. Forster, R. Siegele, J.A. Davies, A.T. Motta, J.A. Faldowski, P.R. Okamoto, Application of ion-beam-analysis techniques to the study of irradiation damage in zirconium alloys, Nucl. Instrum. Methods Phys. Res. Sec. B 118 (1996) 663-669. https://doi.org/10.1016/0168-583X(96)80117-0
  51. T. Diaz de La Rubia, M. Guinan, New mechanism of defect production in metals: a molecular-dynamics study of interstitial-dislocation-loop formation in high-energy displacement cascades, Phys. Rev. Lett. 66 (1991) 2766-2769. https://doi.org/10.1103/PhysRevLett.66.2766
  52. S.X. Wang, L.M. Wang, R.C. Ewing, Irradiation-induced amorphization: effects of temperature, ion mass, cascade size, and dose rate, Phys. Rev. B 63 (2000) 024105. https://doi.org/10.1103/PhysRevB.63.024105
  53. H.M. Naguib, R. Kelly, Criteria for bombardment-induced structural changes in non-metallic solids, Radiat. Eff. 25 (1975) 1-12. https://doi.org/10.1080/00337577508242047
  54. J.L. Brimhall, H.E. Kissinger, L.A. Charlot, Amorphous phase formation in irradiated intermetallic compounds, Radiat. Eff. 77 (1983) 273-293. https://doi.org/10.1080/00337578308228192
  55. S.X. Wang, L.M. Wang, R.C. Ewing, R.H. Doremus, Ion beaminduced amorphization in MgO-$Al_2O_3$-$SiO_2$. I. experimental and theoretical basis, J. Non-Cryst. Solids 238 (1998) 198-213. https://doi.org/10.1016/S0022-3093(98)00694-2
  56. S.X. Wang, L.M. Wang, R.C. Ewing, R.H. Doremus, Ion beaminduced amorphization in MgO-$Al_2O_3$-$SiO_2$. II. empirical model, J. Non-Cryst. Solids 238 (1998) 214-224. https://doi.org/10.1016/S0022-3093(98)00695-4
  57. R. Young, D. Wiles, Profile shape functions in Rietveld refinements, J. Appl. Crystallogr. 15 (1982) 430-438. https://doi.org/10.1107/S002188988201231X
  58. P. Mukherjee, P.M.G. Nambissan, P. Barat, P. Sen, S.K. Bandyopadhyay, J.K. Chakravartty, S.L. Wadekar, S. Banerjee, S.K. Chattopadhyay, S.K. Chatterjee, M.K. Mitra, The study of microstructural defects and mechanical properties in proton-irradiated Zr-1.0%Nb-1.0%Sn-0.1%Fe, J. Nucl. Mater. 297 (2001) 341-344. https://doi.org/10.1016/S0022-3115(01)00630-4
  59. P. Mukherjee, P. Barat, S.K. Bandyopadhyay, P. Sen, S.K. Chottopadhyay, S.K. Chatterjee, M.K. Mitra, Characterisation of microstructural parameters in oxygenirradiated Zr-1.0% Nb-1.0% Sn-0.1% Fe, J. Nucl. Mater. 305 (2002) 169-174. https://doi.org/10.1016/S0022-3115(02)00933-9
  60. P. Mukherjee, A. Sarkar, P. Barat, Microstructural changes in oxygen-irradiated zirconium-based alloy characterised by Xray diffraction techniques, Mater. Charact. 55 (2005) 412-417. https://doi.org/10.1016/j.matchar.2005.09.002
  61. A. Sarkar, P. Mukherjee, P. Barat, Effect of heavy ion irradiation on microstructure of zirconium alloy characterised by X-ray diffraction, J. Nucl. Mater. 372 (2008) 285-292. https://doi.org/10.1016/j.jnucmat.2007.03.217
  62. P.S. Chowdhury, P. Mukherjee, N. Gayathri, M. Bhattacharya, A. Chatterjee, P. Barat, P.M.G. Nambissan, Post irradiated microstructural characterization of Zr-1Nb alloy by X-ray diffraction technique and positron annihilation spectroscopy, Bull. Mater. Sci. 34 (2011) 507-513. https://doi.org/10.1007/s12034-011-0120-6
  63. C. Zhou, X. Liu, C. Ma, B. Wang, Z. Zhang, L. Wei, Positron beam studies of argon-irradiated polycrystal ${\alpha}$-Zr, J. Appl. Phys. 97 (2005) 063511. https://doi.org/10.1063/1.1833573
  64. L. Pagano Jr., A.T. Motta, R.C. Birtcher, The formation of bubbles in Zr alloys under Kr ion irradiation, J. Nucl. Mater. 244 (1997) 295-304. https://doi.org/10.1016/S0022-3115(96)00757-X
  65. G. Ran, J.K. Xu, Q. Shen, J. Zhang, N. Li, L.M. Wang, In situ TEM observation of growth behavior of Kr bubbles in zirconium alloy during post-implantation annealing, Nucl. Instrum. Methods Phys. Res. Sect. B 307 (2013) 516-521. https://doi.org/10.1016/j.nimb.2012.11.085
  66. B.O. Hall, Surface hardening in ion-implanted metals, J. Nucl. Mater. 116 (1983) 123-126. https://doi.org/10.1016/0022-3115(83)90300-8
  67. P. Dayal, D. Bhattacharyya, W.M. Mook, E.G. Fu, Y.Q. Wang, D.G. Carr, O. Anderoglu, N.A. Mara, A. Misra, R.P. Harrison, L. Edwards, Effect of double ion implantation and irradiation by Ar and He ions on nano-indentation hardness of metallic alloys, J. Nucl. Mater. 438 (2013) 108-115. https://doi.org/10.1016/j.jnucmat.2013.02.078
  68. B. Bose, R.J. Klassen, Effect of ion irradiation and indentation depth on the kinetics of deformation during microindentation of Zr-2.5%Nb pressure tube material at $25^{\circ}C$, J. Nucl. Mater. 399 (2010) 32-37. https://doi.org/10.1016/j.jnucmat.2009.12.019
  69. D.O. Northwood, R.A. Herring, Neon ion simulation of neutron induced irradiation growth in zirconium alloys, J. Mater. Eng. 9 (1988) 329-335. https://doi.org/10.1007/BF02834043
  70. J.R. Parsons, C.W. Hoelke, R.W. Gilbert, Ion simulation of neutron irradiation growth in annealed polycrystalline Zr, J. Nucl. Mater. 96 (1981) 169-177. https://doi.org/10.1016/0022-3115(81)90230-0
  71. J.R. Parsons, C.W. Hoelke, Ion simulation of neutron irradiation growth and creep in Zr and Zr-2.5 wt% Nb at 314 K, J. Nucl. Mater. 114 (1983) 103-107. https://doi.org/10.1016/0022-3115(83)90078-8
  72. X.D. Bai, S.G. Wang, J. Xu, J. Bao, H.M. Chen, Y.D. Fan, Effect of self-ion bombardment damage on high temperature oxidation behavior of Zircaloy-4, J. Nucl. Mater. 254 (1998) 266-270. https://doi.org/10.1016/S0022-3115(97)00346-2
  73. J. Xu, X.D. Bai, J. An, Y.D. Fan, Effect of Ar ion irradiation on electrochemical behaviors of zircaloy-4, Appl. Radiat. Isot. 53 (2000) 1005-1010. https://doi.org/10.1016/S0969-8043(99)00253-5
  74. J. Xu, X.D. Bai, J. An, Y.D. Fan, Comparison of electrochemical behaviors of zircaloy-4 irradiated by Ar and Zr ions, J. Mater. Sci. Lett. 19 (2000) 943-945. https://doi.org/10.1023/A:1006755919221
  75. D.Q. Peng, X.D. Bai, X.W. Chen, Q.G. Zhou, X.Y. Liu, R.H. Yu, Effect of self-ion bombardment on the corrosion behavior of zirconium, Nucl. Instrum. Methods Phys. Res. Sect. B 215 (2004) 394-402. https://doi.org/10.1016/j.nimb.2003.09.016

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