Research Progress on the Desorption Behavior of Hydrides in Zirconium Alloys
YANG Zhenfei1, SHI Peng1, AO Bingyun2
1 Institute of Materials, China Academy of Engineering Physics, Jiangyou 621700, China; 2 Science and Technology on Surface Physics and Chemistry Laboratory, China Academy of Engineering Physics, Jiangyou 621908, China
Abstract: Zirconium alloys have been widely used in nuclear reactors due to their strong corrosion resistance and low thermal neutron absorption interface. After more than 60 years’ development, zirconium alloys have evolved from the first generation of zirconium-1 alloys to the second generation of zirconium-2, zirconium-4 alloys and the third generation of N36, ZIRLO, M05 alloys. Hydrogen precipitation will reduce the mecha-nical properties of zirconium alloys. Hydrogen mainly comes from the corrosion reaction between zirconium and water, which enters the metal matrix through diffusion and retains in the matrix. The types and properties of hydrides in zirconium alloys have attracted much attention. So far, there are four types of hydrides, but two of them (ζ-ZrH0.5(bct) and γ-ZrH (fct)) are metastable. Moreover, the presence of ζ phase hydride is extremely short, the current experimental equipment or experimental methods cannot be observed at such a short time scale. Hence, many experimental studies on hydrides are concentrated in δ-ZrH1.4-1.7 (fcc) and ε-ZrH2(fct). The working environment of the zirconium alloys is high temperature, while the retained hydrogen in the matrix will desorb at high temperature and lead to the distortion caused by precipitate phase disappear. During this cycle, many micro defects gradually accumulate inside the material, then accelerate the materials aging. It was found that many researchers used pure ZrH2 powder to study the desorption behavior of hydrogen in zirconium, but the actual serviced zirconium alloys contain other alloying elements, their existence will affect the retention state and desorption behaviors of hydrogen. Thermal desorption spectroscopy (TDS) is one of the effective ways to investigate the retention state of hydrogen and its isotopes in metals and alloys, however, TDS has certain limitations in determining the desorption behavior of hydrogen in zirconium alloy. Besides, the surface of zirconium alloys commonly covered by an oxide layer. When hydrogen diffuses into the oxide layer, the oxygen atoms in the oxide layer will trap some hydrogen atoms by forming hydrogen-oxygen bond. This bond reduces the amount of desorption, delays the desorption, and rises the desorption temperature. Therefore, the increase in desorption temperature on the experimental data does not mean that the actual desorption temperature of the hydride in the matrix, but the process of hydrogen diffusion is blocked by the oxide layer. This review summarizes the research progress of the desorption behavior of zirconium hydride, introduces the structure of hydrides, the source of hydrogen, the hydrogen retention state, the limitations of TDS and the desorption behavior of hydrides respectively, points out the shortco-mings of the research in desorption behavior of zirconium hydrides and prospects the future research directions.
杨振飞, 史鹏, 敖冰云. 锆合金中的氢化物脱附行为研究进展[J]. 材料导报, 2020, 34(5): 5102-5108.
YANG Zhenfei, SHI Peng, AO Bingyun. Research Progress on the Desorption Behavior of Hydrides in Zirconium Alloys. Materials Reports, 2020, 34(5): 5102-5108.
1 Liu P, Du Z Z, Ma L S, et al.Hot Working Technology, 2011, 40(22), 22(in Chinese). 刘鹏, 杜忠泽, 马林生, 等. 热加工工艺, 2011, 40(22), 22. 2 Suman S, Khan M K, Pathak M, et al. Journal of Alloys and Compounds, 2017, 726(1), 107. 3 Xiao Z, Hao M, Guo X, et al. Journal of Nuclear Materials, 2015, 459, 330. 4 Kearns J J. Journal of Nuclear Materials, 1967, 22(3), 292. 5 Kumar N A P K, Szpunar J A, He Z. Journal of Nuclear Materials, 2010, 403(1), 101. 6 Northwood D O, Kosasih U. International Metals Reviews, 1983, 28(1), 92. 7 Dey G K, Banerjee S, Mukhopadhyay P. Le Journal De Physique Colloques, 1982, 43(C4), 327. 8 Dey G K, Banerjee S. Journal of Nuclear Materials, 1984, 125(2), 219. 9 Munakata K, Shinozaki T, Inoue K, et al. Fusion Engineering and Design, 2008, 83(7-9), 1317. 10 Xia T R, Yang H G, Zhan Q, et al. Atomic Energy Science and Technology, 2012, 46(b09), 510(in Chinese). 夏体锐, 杨洪广, 占勤, 等. 原子能科学技术, 2012, 46(b09), 510. 11 Zhao Z, Fernando H J S.Journal of Turbulence, 2008, 9(9), 1. 12 Bair J, Zaeem M A, Schwen D. Acta Materialia, 2017, 123(1), 235. 13 Mishra S, Sivaramakrihnan K S, Asundi M K. Journal of Nuclear Mate-rials, 1972, 45(3), 235. 14 Root J H, Small W M, Khatamian D, et al. Acta Materialia, 2003, 51(7), 2041. 15 Steuwer A, Santisteban J R, Preuss M, et al. Acta Materialia, 2009, 57(1), 145. 16 Barraclough K G, Beevers C J. Journal of the Less Common Metals, 1974, 35(1), 177. 17 Tulk E, Kerr M, Daymond M R. Journal of Nuclear Materials, 2012, 425(1-3), 93. 18 Lanzani L, Ruch M. Journal of Nuclear Materials, 2004, 324(2), 165. 19 Barrow A T W, Korinek A, Daymond M R. Journal of Nuclear Materials, 2013, 432(1-3), 366. 20 Bair J, Zaeem M A. Tonks M. Journal of Nuclear Materials, 2015, 466(1), 12. 21 Maimaitiyili T, Bjerken C, Steuwer A, et al. Journal of Alloys and Compounds, 2017, 695(1), 3124. 22 Motta A T, Couet A, Comstock R J. Annual Review of Materials Research, 2015, 45(1), 311. 23 Lan G Y, Tang B, He Z J, et al. Hot Working Technology, 2017, 46(4), 86(in Chinese). 兰光友, 唐彬, 何祖娟, 等. 热加工工艺, 2017, 46(4), 86. 24 Chu W Y. Hydrogen induced cracking and delayed fracture, Metallurgical Industry Press, China,1983(in Chinese). 褚武扬. 氢损伤和滞后断裂, 冶金工业出版社, 1983. 25 Dai Q X. Metal materials science, Chemical Industry Press, China,2005(in Chinese). 戴起勋. 金属材料学, 化学工业出版社, 2005. 26 Slattery G F. Journal of Nuclear Materials, 1969, 32(30), 30. 27 Erickson W H, Hardie D. Journal of Nuclear Materials, 1964, 13(2), 254. 28 Puls M P. Acta Metallurgica, 1981, 29(12), 1961. 29 Une K, Ishimoto S, Etoh Y, et al. Journal of Nuclear Materials, 2009, 389(1), 127. 30 Couet A, Motta A T, Comstock R J. Journal of Nuclear Materials, 2014, 451(1-3), 1. 31 Ma M, Xiang W, Tang B, et al. Journal of Nuclear Materials, 2015, 467(1), 349. 32 Olander D, Greenspan E, Garkisch H D, et al. Nuclear Engineering and Design, 2009, 239(8), 1406. 33 Lisowski W, Keim E G, Kaszkur Z, et al. Applied Surface Science, 2008, 254(9), 2629. 34 Checchetto R, Gratton L M, Miotello A, et al. Physical Review B, 1998, 58, 4130. 35 Terrani K A, Balooch M, Wongsawaeng D, et al. Journal of Nuclear Materials, 2010, 397(1), 61. 36 Castro F J, Meyer G.Journal of Alloys and Compounds, 2002, 330(1), 59. 37 Hu G X, Cai X, Rong Y H. Fundamentals of material science, Profile of Shanghai Jiao Tong University Press, China, 2003(in Chinese). 胡赓祥, 蔡洵, 戎咏华. 材料科学基础, 上海交通大学出版社, 2003. 38 Fukai Y. Journal of the Less Common Metals, 2005, 172-174(91), 8. 39 Hon J F. Journal of Chemical Physics, 1962, 36(3), 759. 40 Korn C, Goren S D. Physical Review B: Condensed Matter, 1986, 33(1), 68. 41 Majer G, Renz W, Barnes R G. Journal of Physics Condensed Matter, 1999, 6(6), 2935. 42 Ma M, Liang L, Tang B, et al. Journal of Alloys and Compounds, 2015, 645(1), 217. 43 Hu X, Terrani K A, Wirth B D. Journal of Nuclear Materials, 2014, 448(1-3), 87. 44 Lillard R S, Taylor C D, Wermer J R, et al. Journal of Nuclear Mate-rials, 2014, 444(1-3), 49. 45 Wongsawaeng D, Jaiyen S. Journal of Nuclear Materials, 2010, 403(1), 19. 46 Moya J S, Diaz M, Bartolomé J F, et al. Acta Materialia, 2000, 48(18-19), 4749. 47 Hollenberg G W, Simonen E P, Kalinin G, et al. Fusion Engineering and Design, 1995, 28(1-2), 190. 48 Liu W K, Cao X H, Peng S M, et al.Atomic Energy Science and Techno-logy, 2004, 38(5), 419(in Chinese). 刘文科, 曹小华, 彭述明, 等. 原子能科学技术, 2004, 38(5), 419. 49 Wei F G, Tsuzaki K. Metallurgical and Materials Transactions A: Physical Metallurgy and Materials Science, 2006, 37(2), 331. 50 Bhargava G, Gouzman I, Chun C M, et al. Applied Surface Science, 2007, 253(9), 4322. 51 Brundle C R, Chuang T J, Wandelt K. Surface Science, 1977, 68(1), 459. 52 Lin T C. Applied Surface Science, 1997, 119(1), 83. 53 Mathieu H J, Datta M, Landolt D. Journal of Vacuum Science and Technology A Vacuum Surfaces and Films, 1985, 3(2), 331. 54 Aronniemi M, Lahtinen J, Hautojorvi P. Surface and Interface Analysis, 2010, 36(8), 1004. 55 Song W, Du J, Xu Y, et al. Journal of Nuclear Materials, 1997, 246(2), 139. 56 Serra E, Benamati G, Ogorodnikova O V. Journal of Nuclear Materials, 1998, 255(2-3), 105. 57 Chen W, Wang L, Lu S.Journal of Alloys and Compounds, 2009, 469(1), 142. 58 Gabory B D, Motta A T, Wang K. Journal of Nuclear Materials, 2015, 456, 272. 59 Qin W, Nam C, Li H L, et al. Acta Materialia, 2007, 55(5), 1695. 60 Wang H, Wang Y L, Wang X T, et al. Materials Review A: Review Papers, 2013, 27(1), 116(in Chinese). 王辉, 王艳丽, 王西涛, 等. 材料导报:综述篇, 2013, 27(1), 116.
渝公网安备50019002502923号 版权所有：《材料导报》编辑部
2020, Vol. 34 
