Review on Chromium Coated Zirconium Alloy Accident Tolerant Fuel Cladding
YANG Jianqiao1,2, YUN Di1, LIU Junkai1
1 School of Energy and Power Engineering, Xi’an Jiaotong University, Xi’an 710049, China 2 Institute for Applied Materials, Karlsruhe Institute of Technology, Karlsruhe 76344, Germany
Abstract: At present, zirconium alloy with a very low neutron absorption cross section and a high melting point is used as the main component material for nuclear fuel cladding. The Fukushima-Daiichi accident in 2011 made people realize that the zirconium alloy can be degraded very fast in extremely high temperature environment. In order to resist the potential risk of fuel cladding and improve the safety of the nuclear plants, the research on effective and reliable cladding materials for accident tolerant fuel(ATF) system has become the current research hotspot. Preparing a coating on the zirconium alloy surface is one of the adequate methods to improve the oxidation performance of ATF cladding. Se-veral kinds of coating materials were chosen as potential coating materials, including metals, MAX phases, alloys and oxides. Among various coatings under development, Cr coating can effectively improve the high temperature oxidation resistance and high temperature strength of zirconium alloy. Moreover, the Cr coating is relatively easy and cheap to be produced. In a word, the Cr coating is one of the most promising coating materials for ATF, which many researchers focus on now. In this paper, the research progress on the oxidation kinetics of Cr coating, the growth kinetics of Cr-Zr intermediate layer, the long-term oxidation failure mechanism of Cr coating, the factors that lead to the rapid failure of Cr coating and the coating strengthening mechanism from the research around the world are reviewed. This paper can give the cutting edge information on the basic research, the tackle problems in key technologies and the commercialization of the Cr coating ATF cladding materials.
[1] Terrani K A, Zinkle S J, Snead L L. Journal of Nuclear Materials, 2014, 448, 420. [2] Ott L J, Robb K R, Wang D. Journal of Nuclear Materials, 2014, 448, 520. [3] Robb K R. In: Conference Record of the 6th International Topical Mee-ting on Nuclear Reactor Thermalhydraulics. Chicago, 2015, pp. 1213328. [4] Farmer M T, Leibowitz L, Terrani K A, et al. Journal of Nuclear Mate-rials, 2014, 448, 534. [5] Merrill B J, Bragg-Sitton S M, Humrickhouse P W. Nuclear Engineering and Design, 2017, 315, 170. [6] Yao M Y, Li S L, Zhang X, et al. Acta Metallurgica Sinica, 2011, 47(7), 865(in Chinese) 姚美意, 李士炉, 张欣, 等. 金属学报, 2011, 47(7), 865. [7] Yao M Y, Zhou B X, Li Q, et al. Shanghai Metals, 2008(6), 1(in Chinese) 姚美意, 周邦新, 李强, 等. 上海金属, 2008(6), 1. [8] Liu J K, Zhang X H, Yun D. Materials Reports A:Review Papers. 2018, 32(11), 1757(in Chinese). 刘俊凯, 张新虎, 恽迪. 材料导报:综述篇, 2018, 32(11), 1757. [9] Brachet J, Guilbert T, Le Saux M, et al. In: Conference Record of the Topfuel 2018.Prague,2018.https:∥hal.archives-ouvertes.fr/cea-02328975. [10] Han X, Xue J, Peng S, et al. Corrosion Science, 2019, 156, 117. [11] Kim H G, Kim I H, Jung Y I, et al. In: Proceeding of LWR Fuel Performance Meeting. USA, 2013, pp. 842. [12] Wei T, Zhang R, Yang H, et al. Corrosion Science, 2019, 158, 108077. [13] Yeom H, Maier B, Johnson G, et al. Journal of Nuclear Materials, 2019, 526, 151737. [14] Tang C, Klimenkov M, Jaentsch U, et al. Surface and Coatings Techno-logy, 2017, 309, 445. [15] Tang C, Steinbrück M, Groe M, et al. Journal of Nuclear Materials, 2017, 490, 130. [16] Tang C, Steinbrueck M, Stueber M, et al. Corrosion Science, 2018, 135, 87. [17] Gigax J G, Kennas M, Kim H, et al. Journal of Nuclear Materials, 2019, 523, 26. [18] Tunes M A, Harrison R W, Donnelly S E, et al. Acta Materialia, 2019, 169, 237. [19] Kim J M, Ha T H, Kim I H, et al. Metals, 2017, 7(2), 59. [20] Kim J M, Ha T H, Park J S, et al. Metals, 2016, 6(2), 29. [21] Lenling M, Yeom H, Maier B, et al. JOM Journal of the Minerals Metals and Materials Society, 2019, 71, 2868. [22] Massey C P, Terrani K A, Dryepondt S N, et al. Journal of Nuclear Materials, 2016, 470, 128. [23] Krejcˇí J, evecˇek M, Cvrcek L, et al. In: Proceedings of the 20th International Corrosion Congress. Prague, 2017. [24] Jung Y I, Kim H G, Guim H U, et al. Applied Surface Science, 2018, 429, 272. [25] Sidelev D V, Bleykher G A, Krivobokov V P, et al. Surface and Coa-tings Technology, 2016, 308, 168. [26] Brachet J C, Le Saux M, Lezaud-Chaillioux V, et al. In:Conference Record of the Topfuel 2016-Light Water Reactor (LWR) Fuel Performance Meeting. Boise, 2016,pp.1173. [27] Park J H, Kim H G, Park J Y, et al. Surface and Coatings Technology, 2015, 280, 256. [28] Brachet J C, Idarraga-Trujillo I, Le Flem M, et al. Journal of Nuclear Materials, 2019, 517, 268. [29] Brachet J C, Rouesne E, Ribis J, et al. Corrosion Science, 2020, 167, 108537. [30] Michau A, Gazal Y, Addou F, et al. Surface and Coatings Technology, 2019, 375, 894. [31] Michau A, Maury F, Schuster F, et al. Applied Surface Science, 2017, 422, 198. [32] Michau A, Maury F, Schuster F, et al. Surface and Coatings Technology, 2017, 332, 96. [33] Michau A, Maury F, Schuster F, et al. Surface and Coatings Technology, 2018, 349, 1048. [34] Michau A, Maury F, Schuster F, et al. Coatings, 2018, 8(6), 220 [35] Park D J, Kim H G, Jung Y I, et al. Journal of Nuclear Materials, 2016, 482, 75. [36] Hu X, Dong C, Wang Q, et al. Journal of Nuclear Materials, 2019, 519, 145. [37] Wang Y, Zhou W, Wen Q, et al. Surface and Coatings Technology, 2018, 344, 141. [38] Maier B R, Yeom H, Johnson G, et al. Journal of Nuclear Materials, 2018, 512, 320. [39] evecˇek M, Gurgen A, Seshadri A, et al. Nuclear Engineering and Technology, 2018, 50, 229. [40] Royer L, Ledoux X, Mathieu S, et al. Oxidation of Metals, 2010, 74, 79. [41] Kim H G, Kim I H, Jung Y I, et al. Journal of Nuclear Materials, 2015, 465, 531. [42] He X, Tian Z, Shi B, et al. Annals of Nuclear Energy, 2019, 132, 243. [43] Ribis J, Wu A, Brachet J C, et al. Journal of Materials Science, 2018, 53, 9879. [44] Wu A, Ribis J, Brachet J C, et al. Journal of Nuclear Materials, 2018, 504, 289. [45] Sigle W, Krmer S, Varshney V, et al. Ultramicroscopy, 2003, 96, 565. [46] Vander Sande J B, Bement A L. Journal of Nuclear Materials, 1974, 52(1), 115. [47] Saporiti F, Bozzano P, Versaci R, et al. Hyperfine Interactions, 2002, 139, 379. [48] Laves F. Theory of alloy phases, American Society for Metals, USA, 1955, pp. 232. [49] Zhu J, Liu C, Liaw P. Intermetallics, 1999, 7, 1011. [50] Xiang W, Ying S. China Nuclear Information Centre, 2001, 33(20).https:∥www.osti.gov/etdeweb/biblio/20247728. [51] Nicolai L, De Tendler R. Journal of Nuclear Materials, 1979, 82, 439. [52] Mehrer H. New Series Group III, 1990, 26, 747. [53] Yeom H, Dabney T, Johnson G, et al. The International Journal of Advanced Manufacturing Technology, 2019, 100, 1373. [54] Gong W, Zhang H, Wu C, et al. Corrosion Science, 2013, 77, 391. [55] Neumann G, Tuijnc.In: Self-diffusion and Impurity Diffusion in Pure Metals. Elsevier, UK, 2011, pp. 69. [56] Balart S, Varela N, De Tendler R. Journal of Nuclear Materials, 1983, 119, 59. [57] Krejcˇí J, Kabátová J, Manoch F, et al. Nuclear Engineering and Technology, 2020, 52, 597. [58] Leistikow S, Schanz G. Nuclear Engineering and Design, 1987, 103, 65. [59] Dupin N, Ansara I, Servant C, et al. Journal of Nuclear Materials, 1999, 275, 287. [60] Andersson J O. International Journal of Thermophysics, 1985, 6, 411. [61] Domagala R, Mcpherson D. JOM Journal of the Minerals Metals and Materials Society, 1954, 6, 238. [62] Steinbrück M, Bttcher M. Journal of Nuclear Materials, 2011, 414, 276. [63] Urbanic V, Heidrick T. Journal of Nuclear Materials, 1978, 75(2), 251. [64] D'auria F, Dusic M, Dutton L, et al. IAEA Specific Safety Guide, IAEA, Austria, 2009,pp.8. [65] Terrani K A, Parish C M, Shin D, et al. Journal of Nuclear Materials, 2013, 438, 64. [66] Steinbrück M, Groe M, Sepold L, et al. Nuclear Engineering and Design, 2010, 240, 1714. [67] Cheng B, Chou P, Kim Y J. In: Conference Record of 2014 Water Reactor Fuel Performance Meeting. Sendai, 2014, pp. 784. [68] Cheng B. Atw Internationale Zeitschrift fuer Kernenergie, 2013, 58(3), 158. [69] Kim H G, Kim I H, Park J Y, et al. In: Conference Record of Zirconium in the Nuclear Industry: 17th International Symposium. West Conshohocken, 2014, pp. 346. [70] Li R, Liu T. Nuclear Power Engineering, 2019, 40(4), 74(in Chinese) 李锐, 刘彤. 核动力工程, 2019, 40(4), 74. [71] Yang Z, Niu Y, Xue J, et al. Materials and Corrosion, 2019, 70, 37. [72] Brova M J, Alat E, Pauley M A, et al. Surface and Coatings Technology, 2017, 331, 163. [73] Kim H G, Kim I H, Jung Y I, et al. Journal of Nuclear Materials, 2018, 510, 93. [74] Hu X G, Dong C, Chen B Q, et al. Surface Technology, 2019, 48(2), 217(in Chinese). 胡小刚, 董闯, 陈宝清, 等. 表面技术, 2019, 48(2), 217. [75] Duan Z, Yang H, Satoh Y, et al. Nuclear Engineering and Design, 2017, 316, 131. [76] Shewfelt R. Research Mechanica, 1988, 25, 261. [77] Veshchunov M, Shestak V. Journal of Nuclear Materials, 2015, 461, 129. [78] Steinbrück M, Birchley J, Boldyrev A V, et al. Progress in Nuclear Energy, 2010, 52, 19. [79] Billone M, Yan Y, Burtseva T, et al. Cladding embrittlement during postulated loss-of-coolant accidents. Argonne National Lab, USA, 2008, pp. 17. [80] Bischoff J, Delafoy C, Chaari N, et al. Top Fuel, 2018, 2018, A0152. [81] Bischoff J, Delafoy C, Vauglin C, et al. Nuclear Engineering and Technology, 2018, 50, 223. [82] Xiao W, Chen H, Liu X, et al. Journal of Nuclear Materials, 2019, 526, 151777. [83] Xiao W, Deng H, Zou S, et al. Journal of Nuclear Materials, 2018, 509, 542. [84] Gautier C, Machet J. Thin Solid Films, 1996, 289, 34. [85] Sarakinos K, Alami J, Konstantinidis S. Surface and Coatings Technology, 2010, 204, 1661. [86] Anders A. Journal of Vacuum Science & Technology A: Vacuum, Surfaces, and Films, 2010, 28, 783. [87] Samuelsson M, Lundin D, Jensen J, et al. Surface and Coatings Techno-logy, 2010, 205, 591. [88] Musil J, Rajsky A, Bell A, et al. Journal of Vacuum Science & Technology A: Vacuum, Surfaces, and Films, 1996, 14, 2187. [89] Billard A, Mercs D, Perry F, et al. Surface and Coatings Technology, 1999, 116-119, 721. [90] Cormier P A, Thomann A L, Dolique V, et al. Thin Solid Films, 2013, 545, 44. [91] Petrov I, Barna P B, Hultman L, et al. Journal of Vacuum Science & Technology A: Vacuum, Surfaces and Films, 2003, 21, 117. [92] Grudinin V A, Bleykher G A, Sidelev D V, et al. Surface and Coatings Technology, 2019, 375, 352. [93] Gigax J G, Kennas M, Kim H, et al. Journal of Nuclear Materials, 2019, 519, 57. [94] Fan S Q, Yang G J, Li C, et al. Journal of Thermal Spray Technology, 2006, 15, 513. [95] Girardin G, Meier R, Jatuff F, et al. In: Conference Record of TopFuel 2018. Prague, 2018. [96] Tang C, Jianu A, Steinbrueck M, et al. Journal of Nuclear Materials, 2018, 511, 496. [97] Tunes M A, Da Silva F C, Camara O, et al. Journal of Nuclear Mate-rials, 2018, 512, 239. [98] Tunes M A, Vishnyakov V M, Camara O, et al. Materials Today Energy, 2019, 12, 356. [99] Sidelev D V, Bleykher G A, Bestetti M, et al. Vacuum, 2017, 143, 479. [100] Sidelev D V, Kashkarov E B, Syrtanov M S, et al. Surface and Coatings Technology, 2019, 369, 69. [101] Heuser B J, Stubbins J, Kozlowski T, et al.Engineered Zircaloy Cladding Modifications for Improved Accident Tolerance of LWR Nuclear Fuel. USDOE Office of Nuclear Energy. USA, 2017,pp.56. [102] Tallman D J, Hoffman E N, Caspi E N, et al. Acta Materialia, 2015, 85, 132. [103] Alat E, Motta A T, Comstock R J, et al. Surface and Coatings Techno-logy, 2015, 281, 133. [104] Alat E, Motta A T, Comstock R J, et al. Journal of Nuclear Materials, 2016, 478, 236. [105] Park D J, Kim H G, Park J Y, et al. Corrosion Science, 2015, 94, 459. [106] Park D J, Kim H G, Jung Y I, et al. Fusion Engineering and Design, 2019, 139, 81. [107] Jeong-Min K, Tae-Hyung H, Joon-Sik P, et al. Transactions of Nonferrous Metals Society of China, 2016, 26, 2603. [108] Jung Y I, Kim H G, Kim I H, et al. Journal of Nuclear Materials, 2014, 455, 586. [109] Huang H, Qiu C J, Chen Y, et al. China Surface Engineering, 2018, 31(2), 51(in Chinese). 黄鹤, 邱长军, 陈勇, 等. 中国表面工程, 2018, 31(2), 51.
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2022, Vol. 36 
