事故容错锆包壳表面FeCrAl合金涂层的研究进展

doi:10.11896/cldb.22110325

Abstract
Figure/Table
References
Related Citation (15)

Download:

Full Text ( PDF ) (23814KB)
Export: BibTeX | EndNote (RIS)

Abstract The Fukushima nuclear accident in Japan exposed the fatal deficiency of zircaloy fuel cladding under loss of coolant accident (LOCA) conditions, i.e., the reaction of zirconium with high-temperature steam. As a result, a research focus on the accident tolerant fuel (ATF) cladding materials with high security was triggered rapidly. Surface coating technologies provide a promising avenue for effectively improving the accident tolerance of zircaloy cladding in service. FeCrAl alloy, due to its excellent oxidation resistance and mechanical properties at high temperatures, becomes one of the candidate coating materials with great development potential for ATF claddings. This paper mainly reviewed the preparation technologies, composition and microstructure, service performances (including mechanical properties, oxidation resistance, corrosion resistance and anti-irradiation), and the relevant failure mechanisms of FeCrAl alloy coating. Moreover, the existed problems of FeCrAl coating/zircaloy cladding system in the engineering applications were also discussed, with prospecting the future direction of development.

Key words： zircaloy cladding surface technology FeCrAl coatings microstructure service performances failure mechanisms

Published: 25 June 2024 Online: 2024-07-17

CLC number:

TG178

Fund:National Natural Science Foundation of China (U2067219, U20B2027, 52001247, 92163201) and the Initiative Postdocs Supporting Program (BX20190266).

	Service
	E-mail this article
	Add to my bookshelf
	Add to citation manager
	E-mail Alert
	RSS
	Articles by authors
	WANG Yaheng
	ZUO Jiadong
	WANG Yaqiang
	ZHANG Jinyu
	WU Kai
	LIU Gang
	SUN Jun

Cite this article:

WANG Yaheng,ZUO Jiadong,WANG Yaqiang, et al. Research Progress of FeCrAl Coatings on Accident-Tolerant Zircaloy Cladding Surface[J]. Materials Reports, 2024, 38(12): 22110325-11.

URL:

http://www.mater-rep.com/EN/10.11896/cldb.22110325 OR http://www.mater-rep.com/EN/Y2024/V38/I12/22110325

1 Lei Y M. Design, synthesis and properties of protective coatings for accident tolerant fuels. Ph. D. Thesis, University of Science and Technology of China, China, 2021(in Chinese).
雷一明. 几种事故容错燃料包壳涂层的设计、制备与性能研究. 博士学位论文, 中国科学技术大学, 2021.
2 Rickover H G, Geiger L D, Lustman B. Energy Research and Development Administration, DOI:10.2172/4240391.
3 Gadiyar H. In: Proceedings of Symposium on Zirconium Alloys For Reactor Components. Bhabha Atomic Research Centre:Bombay, 1992, pp.149.
4 Cox B. Journal of Nuclear Materials, 2005, 336(2), 331.
5 Kashkarov E, Afornu B, Sidelev D, et al. Coatings, 2021, 11(5), 557.
6 Bischoff J, Delafoy C, Vauglin C, et al. Nuclear Engineering and Technology, 2018, 50(2), 223.
7 Kim H G, Yang J H, Kim W J. Nuclear Engineering and Technology, 2016, 48(1), 1.
8 Cheng B, Chou P, Kim Y J. EPJ Nuclear Sciences & Technologies, 2016, 2, 1.
9 Terrani K A, Zinkle S J, Snead L L. Journal of Nuclear Materials, 2014, 448(1), 420.
10 Yueh K, Terrani K A. Journal of Nuclear Materials, 2014, 448(1), 380.
11 Liu J K, Zhang X H, Yun D. Materials Reports, 2018, 32(11), 1757. (in Chinese)
刘俊凯, 张新虎, 恽迪. 材料导报, 2018, 32(11), 1757.
12 Baek J H, Jeong Y H. Journal of Nuclear Materials, 2008, 372(2), 152.
13 Kim H G, Hwan J Y. Nuclear Engineering and Technology, 2010, 42(2), 193.
14 Duan Z G, Yang H L, Satoh Y, et al. Nuclear Engineering and Design, 2017, 316, 131.
15 Maier B R, Garcia-Diaz B L, Hauch B, et al. Journal of Nuclear Mate-rials, 2015, 466, 712.
16 Usui T, Sawada A, Amaya M, et al. Journal of Nuclear Science and Technology, 2015, 52(10), 1318.
17 Xiao W W, Deng H, Zou S L, et al. Journal of Nuclear Materials, 2018, 509, 542.
18 Wang X J, Liu Y H, Feng S, et al. Chinese Journal of Vacuum Science and Technology, 2018, 38(4), 332. (in Chinese)
王晓婧, 刘艳红, 冯硕, 等. 真空科学与技术学报, 2018, 38(4), 332.
19 Tang C C, Steinbrueck M, Stueber M, et al. Corrosion Science, 2018, 135, 87.
20 Dong Y, Ge F F, Meng F P, et al. Surface & Coatings Technology, 2018, 350, 841.
21 Dong Y. Preparation and oxidation in high-temperature steam of Cr-AI-Si(-N) protective coatings coated on Zr alloys. Master's Thesis, Chengdu University of Technology, China, 2018 (in Chinese).
董悦. Zr合金表面Cr-Al-Si(-N)防护涂层的制备及其抗高温水蒸气氧化研究. 硕士学位论文, 成都理工大学, 2018.
22 Xiao X, Wang Y Q, Zhang J Y, et al. Materials China, 2022, 41(6), 445(in Chinese).
肖珣, 王亚强, 张金钰, 等. 中国材料进展, 2022, 41(6), 445.
23 Kim H G, Kim I H, Jung Y I, et al. Journal of Nuclear Materials, 2015, 465, 531.
24 Zhong W C, Mouche P A, Heuser B J. Journal of Nuclear Materials, 2018, 498, 137.
25 Yeom H, Maier B, Johnson G, et al. Journal of Nuclear Materials, 2018, 507, 306.
26 Yeom H, Maier B, Johnson G, et al. Journal of Nuclear Materials, 2019, 526, 151737.
27 Yang H Y, Zhang R Q, Peng X M, et al. Surface Technology, 2017, 46(1), 69(in Chinese).
杨红艳, 张瑞谦, 彭小明, 等. 表面技术, 2017, 46(1), 69.
28 He L X, Liu C H, Lin J H, et al. Journal of Nuclear Materials, 2021, 551, 152966.
29 Yang H Y, Chen Q S, Zhang R Q, et al. Nuclear Power Engineering, 2020, 41(S1), 200(in Chinese).
杨红艳, 陈青松, 张瑞谦, 等. 核动力工程, 2020, 41(S1), 200.
30 Wang Y D, Zhou W C, Wen Q L, et al. Surface & Coatings Technology, 2018, 344, 141.
31 Li T, Liu T. Nuclear Power Engineering, 2019, 40(4), 65(in Chinese).
李锐, 刘彤. 核动力工程, 2019, 40(4), 65.
32 Jr C V K, Dennis H, Phillip L, et al. Journal of Thermal Spray Techno-logy, 2005, 14(3), 330.
33 Shang C. China Steel Focus, 2021(5), 35(in Chinese).
尚灿. 冶金管理, 2021(5), 35.
34 Chen Q S. Investigation of the preparation and accident-tolerant properties of metal coating on zirconium alloy. Master's Thesis, Chengdu University of Technology, China, 2020(in Chinese).
陈青松. 锆合金表面事故容错金属涂层的制备及相关性能研究. 硕士学位论文, 成都理工大学, 2020.
35 Yamamoto Y, Field K G, Snead L L. Iaea Tecdoc Series, 2016, 47(29), 47080117.
36 Zhang Y Y, Sun H Y, Wang H, et al. Materials Science & Engineering A, 2021, 826, 142003.
37 Yamamoto Y, Pint B A, Terrani K A, et al. Journal of Nuclear Mate-rials, 2015, 467, 703.
38 Huang X, Li X Y, Fang X D, et al. Journal of Materials Engineering, 2020, 48(3), 19(in Chinese).
黄希, 李小燕, 方晓东, 等. 材料工程, 2020, 48(3), 19.
39 Satoru K, Takayuki T. Scripta Materialia, 2010, 63(11), 1104.
40 Kim I H, Jung Y I, Kim H G, et al. Surface & Coatings Technology, 2021, 411, 126915.
41 Zhong W C, Mouche P A, Han X C, et al. Journal of Nuclear Materials, 2016, 470, 327.
42 Gigax J G, Kennas M, Kim H, et al. Journal of Nuclear Materials, 2019, 519, 57.
43 Josefsson H, Liu R, Svensson J E, et al. Materials and Corrosion, 2005, 56(11), 801.
44 Badini C, Laurella F. Surface & Coatings Technology, 2001, 135(2), 291.
45 Yin L, Jurewicz T. B, Larsen M, et al. Journal of Nuclear Materials, 2021, 554, 153090.
46 Zhou J, Qiu S Y, Du P N, et al. Materials Reports, 2017, 31(S2), 47(in Chinese).
周军, 邱绍宇, 杜沛南, 等. 材料导报, 2017, 31(S2), 47.
47 Field K G, Hu X X, Littrell K C, et al. Journal of Nuclear Materials, 2015, 465, 746.
48 Field K G, Briggs S A, Sridharan K, et al. Journal of Nuclear Materials, 2017, 489, 118.
49 Lei Y, Zhang H S, Mao J J, et al. Nuclear Power Engineering, 2022, 43(1), 97(in Chinese).
雷阳, 张海生, 毛建军, 等. 核动力工程, 2022, 43(1), 97.
50 Deng P, Peng Q J, Han E H, et al. Corrosion Science, 2017, 127, 91.
51 Wang P, Grdanovska S, Bartels D M, et al. Journal of Nuclear Mate-rials, 2020, 533, 152108.
52 Hao S Z, Zhao L M, He D Y. Nuclear Instruments and Methods in Physics Research Section B, 2013, 312, 97.
53 Haley J C, Briggs S A, Edmondson P D, et al. Acta Materialia, 2017, 136, 390.
54 Jiang G Y, Xu D H, Feng P, et al. Journal of Alloys and Compounds, 2021, 869, 159235.
55 Ackland G. Science, 2010, 327(5973), 1587.
56 Yutani K, Kishimoto H, Kasada R, et al. Journal of Nuclear Materials, 2007, 367, 423.
57 Rebak R B. EPJ Nuclear Sciences & Technologies, 2017, 3, 34.
58 Alat E, Motta A T, Comstock R J, et al. Surface & Coatings Technology, 2015, 281, 133.
59 Zhang W, Tang R, Yang Z B, et al. Surface & Coatings Technology, 2018, 347, 13.
60 Pint B A, Terrani K A, Brady M P, et al. Journal of Nuclear Materials, 2013, 440(1), 420.