熔盐堆用镍基合金在熔融氟盐中的腐蚀研究进展

doi:10.11896/cldb.18080069

Abstract
Figure/Table
References
Related Citation (15)

Download:

Full Text ( PDF ) (1474KB)
Export: BibTeX | EndNote (RIS)

Abstract Molten salt reactor (MSR) is the only liquid fueled one in the Generation IV of advanced nuclear reactors, which has attracted worldwide attention due to its incomparable advantages in thermal conversion efficiency, neutron economy, inherent safety, online fuel cycle and nuclear waste treatment. The choice of molten salt is crucial to the operation safety and efficiency of MSR. Fluoride molten salts such as LiF-BeF₂ (FLiBe) and LiF-NaF-KF (FLiNaK) have a series of excellent thermal physicochemical properties such as small cross section for thermal neutron absorption, high thermal conductivity, high specific heat capacity, good fluidity, low vapor pressure at high temperature, and good high temperature stability. Fluoride molten salts are generally considered as the optimal coolant and fuel. Currently, Ni-based alloy is used as main structural material of MSR at home and abroad. However, the extremely high temperature corrosion of molten fluoride salt puts forward some harsh requirements for the Ni-based alloys.Currently, the research focus on the corrosion behavior of Ni-based alloys in molten fluoride salt of MSR includes two aspects: one is the factors affecting the hot corrosion behavior of Ni-based alloy in molten fluoride salt and the relative mechanism, while the other is how to improve the corrosion resistance of Ni-based alloys in the high-temperature molten salt. It is generally believed that the corrosion mechanism of Ni-based alloy in molten fluoride salt includes the following four types: essential corrosion, corrosion caused by oxidizing impurities, temperature driven corrosion and corrosion caused by different materials. Therefore, the main factors can be attributed to two aspects: the alloy itself and the molten salt corrosion environment. In terms of the alloy itself, it is mainly affected by the alloy elements (Ni, Cr, Mo, Fe, Si, etc.) and content, the alloy microstructure (grain boundary characteristics, microstructural defects, etc.). Regarding the molten salt corrosion environment, the effects of molten salt components, impurities and corrosion products in molten salt, molten salt temperature, crucible material and fission products are mainly discussed. Besides, the main strategies to improve the corrosion resistance of Ni-based alloys are summarized. For the Ni-based alloys, the methods such as microalloying (adding Ti, RE, etc.), grain boundary engineering treatment, and ceramic phase reinforced composite technology are reviewed. For molten salt, it includes purification of molten salt and addition of pure metals (such as Zr, Be, Li, etc.) to reduce the redox potential of molten salt. In addition, surface modification techniques such as electroplating, laser cladding, chemical vapor deposition, and plasma spraying have been used to prepare metal coatings (Ni, Co, Mo, NiCoCrAlY, etc.) and ceramic coatings (AlN, carbide such as SiC) on Ni-based alloys for the corrosion resistance improvement. This paper mainly summarizes the progress of the above two research focuses, i.e., the factors affecting the hot corrosion behavior of Ni-based alloy in molten fluoride salt and the relative mechanism, as well as the methods improving the corrosion resistance of Ni-based alloys in the high-temperature molten salt. On the basis of some key fundamental problems in the compatibility between Ni-based alloy and strong corrosion-resis-tant molten fluoride salt, the future research directions and tendency of Ni-based alloy applied in the molten fluoride salt are proposed. This paper may provide important ideas for investigating and exploring the corrosion-resistant materials in high-temperature fluoride salt

Key words： Ni-based alloys molten fluoride salt corrosion influence factors improvement methods

Published: 21 May 2019

CLC number:

TG174.21

Fund:This work is finacially supported by Research Foundation of Education Bureau of Hunan Province (15K108), National Natural Science Foundation of China (51474130), Qinghai Major Science and Technology Projects(2017-GX-A3).

About author:: Hongmei Zhu, Ph.D., associate professor, master supervisor. In June 2011, she graduated from South China University of Technology, majoring in material proces-sing engineering. She has been studying in the University of Sydney in Australia for 18 months and visited Purdue University for one year. She is currently the director of the institute of metallic materials and micro-manufacturing in the University of South China, and a member of the Youth Working Committee of Surface Engineering Institution of Chinese Mechanical Engineering Society. Her research interest is the safety service and surface modification technology of nuclear metallic materials. Currently, she is hosting six natural science foundation project including national, provincial and municipal levels, and published over 20 SCI/EI papers as the first author/corresponding author.Changjun Qiu, Ph.D., professor, doctoral supervisor. In June 2003, he received his doctoral degree from Central South University. He is currently the leader of mechanical engineering discipline in Hunan province, the leader of Hunan provincial science and technology innovation team-nuclear energy equipment and safety service technology, and the director of Hunan provincial key laboratory-equipment safety service technology under special environment. His research interests are nuclear facility safety engineering and decommissioning technology, safety service and surface modification technology of nuclear metallic materials. He has hosted 1 Major Research Plan of the National Natural Science Foundation of China, 3 General Programs of the National Natural Science Foundation of China, and 1 subitem of the National Major Scientific and Technological Special Project. He published over 100 papers with high impact factor.

	Service
	E-mail this article
	Add to my bookshelf
	Add to citation manager
	E-mail Alert
	RSS
	Articles by authors
	ZHU Hongmei
	LI Baichun
	ZHU Jinyun
	QIU Changjun
	TANG Zhongfeng

Cite this article:

ZHU Hongmei,LI Baichun,ZHU Jinyun, et al. Research Progress on Corrosion of Ni-Based Alloy in Molten Fluorine Salt of Molten Salt Reactor[J]. Materials Reports, 2019, 33(11): 1813-1820.

URL:

http://www.mater-rep.com/EN/10.11896/cldb.18080069 OR http://www.mater-rep.com/EN/Y2019/V33/I11/1813

1 Uhlí J. Journal of Nuclear Materials,2007,360(1),6.
2 Qiu H Z, Zhang D L, Shu G H, et al. Atomic Energy Science and Technology,2009,43(s),64(in Chinese).
秋穗正,张大林,苏光辉,等.原子能科学技术,2009,43(s),64.
3 Jérôme Serp, Michel Allibert, Ondrej Benes, et al. Progress in Nuclear Energy,2014,77,308.
4 Beneš O, Konings R J M. Journal of Fluorine Chemistry,2009,130(1),22.
5 Wang Y, Tang Z F, Xie L D, et al. Chemistry,2013,76(4),307(in Chinese).
汪洋,唐忠锋,谢雷东,等.化学通报,2013,76(4),307.
6 Patel N S, Pavlík Viliam, Boa Miroslav. Critical Reviews in Solid State and Materials Sciences,2017,42(1),83.
7 Wang Y, Zeng C, Li W. Corrosion Science,2018,136,180.
8 Olson L C, Ambrosek J W, Sridharan K, et al. Journal of Fluorine Chemistry,2009,130(1),67.
9 Xu Y X, Zeng C L. Journal of Chinese Society for Corrosion and Protection,2014,34(3), 211(in Chinese).
徐雅欣,曾潮流.中国腐蚀与防护学报,2014,34(3),211.
10 Wang Y, Liu H, Zeng C. Journal of Fluorine Chemistry,2014,165,1.
11 Sona C S, Gajbhiye B D, Hule P V, et al. Corrosion Engineering, Science and Technology,2014,49(4),287.
12 Ouyang F Y, Chang C H, Kai J J. Journal of Nuclear Materials,2014,446(1-3),81.
13 Qiu J, Zou Y, Li Z J, et al. Nuclear Techniques,2015,38(7),070601(in Chinese).
邱杰,邹杨,李志军,等.核技术,2015,38(7),070601.
14 Zhu Y, Qiu J, Hou J, et al. Journal of Nuclear Materials,2017,492,122.
15 Li X, He S, Zhou X, et al. Journal of Nuclear Materials,2015,464,342.
16 Qiu J, Zou Y, Yu G J, et al. Journal of Nuclear Science and Technology,2015,26,060602.
17 Ouyang F Y, Wang Y S, Wang M Y, et al. Corrosion Engineering, Science and Technology,2014,49(2),101.
18 Gehlbach R, McCoy H. In: International Symposium on Structural Stabi-lity in Superalloys, Seven Springs,1968,pp.346.
19 Holcomb D E, Muralidharan G, Wilson D F. U.S. Patent, EP9540714,2017.
20 Dai Q, Ye X X, Ai H, et al. Corrosion Science,2018,133,349.
21 Liu T, Dong J S, Xie G, et al. Materials Science and Engineering: A,2016,656,75.
22 Liu S, Ye X X, Jiang L, et al. Materials Science and Engineering: A,2016,655,269.
23 Wang Y L, Wang Q, Liu H J, et al. Corrosion Science,2016,109,43.
24 Wang Y L, Wang Q, Liu H J, et al. RSC Advances,2015,5(41),32755.
25 Lin J B, Li A G, He S M, et al. Nuclear Techniques,2014,37(5),050601(in Chinese).
林建波,李爱国,何上明,等.核技术,2014,37(5),050601.
26 Lin J, Li A, Yu X, et al. Journal of Nuclear Science and Technology,2014,51(2),175.
27 Zhu H, Holmes R, Hanley T, et al. Corrosion Science,2017,125,184.
28 Zhu H, Holmes R, Hanley T, et al. Corrosion Science,2015,91,1.
29 Williams D F, Toth L M, Clarno K T. Assessment of candidate molten salt coolants for the advanced high temperature reactor (AHTR), Department of Energy, United States,2006.
30Šimo T, Matal O, Nesvadba L, et al. Zeitschrift für Naturforschung A,2007,62(12),769.
31 Ding X B, Sun H, Yu G J, et al. Journal of Chinese Society for Corrosion and Protection,2015,35(6),543(in Chinese).
丁祥彬,孙华,俞国军,等.中国腐蚀与防护学报,2015,35(6),543.
32 Sawant S S, Gajbhiye B D, Tyagi S, et al. Indian Chemical Engineer,2017,59(3),242.
33 Delpech S, Cabet C, Slim C, et al. Materials Today,2010,13(12),34.
34 Ouyang F Y, Chang C H, You B C, et al. Journal of Nuclear Materials,2013,437(1-3),201.
35 Wang Y, Liu H, Yu G, et al. Journal of Fluorine Chemistry,2015,178,14.
36 Hou J, Yu G, Zeng C, et al. Journal of Fluorine Chemistry,2016,191,110.
37 Liu K, Xu L, Liu Z, et al. Nuclear Techniques,2015,38(2),020602(in Chinese).
刘可,徐良,刘哲,等.核技术,2015,38(2),020602.
38 Ye X X, Ai H, Guo Z, et al. Corrosion Science,2016,106,249.
39 Yin H, Qiu J, Liu H, et al. Corrosion Science,2018,131,355.
40 Lei Q, Liu K, Gao J, et al. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms,2017,404,185.
41 Rosenthal M W, Kasten P R, Briggs R B. Nuclear Applications and Technology,1970,8(2),107.
42 Wang Y, Zeng C, Li W. Corrosion Science,2018,136,180.
43 Scarlat R O, Laufer M R, Blandford E D, et al. Progress in Nuclear Energy,2014,77,406.
44 Olson L, Sridharan K, Anderson M, et al. Journal of Nuclear Materials,2011,411(1-3),51.
45 Fukumoto K, Fujimura R, Yamawaki M, et al. Journal of Nuclear Science and Technology,2015,52(10),1323.
46 Rosenthal M W, Haubenreich P N, Briggs R B. The development status of molten-salt breeder reactors,Oak Ridge, Tennessee,1972, pp.4812.
47 Ai H, Hou J, Ye X X, et al. Journal of Nuclear Materials,2018,503,116.
48 Sellers R S, Cheng W J, Kelleher B C, et al. Nuclear Technology,2014,188(2),192.
49 Cheng H, Leng B, Chen K, et al. Corrosion Science,2015,97,1.
50 McCoy H E, Beatty R L, Cook W H, et al. Nuclear Applications and Technology,1970,8(2),156.
51 Pint B A, Terrani K A, Brady M P, et al. Journal of Nuclear Materials,2013,440(1-3),420.
52 Ignatiev V, Surenkov A, Gnidoy I, et al. Journal of Nuclear Materials,2013,440(1-3),243.
53 Ignatiev V, Surenkov A. Journal of Nuclear Materials,2013,441(1-3),592.
54 Telang A, Gill A S, Tammana D, et al. Materials Science and Enginee-ring: A,2015,648,280.
55 Nie S H, Liang Z Q. Corrosion and Protection,2018(1),29(in Chinese).
聂书红,梁政强.腐蚀与防护,2018(1),29.
56 Shi P, Hu R, Zhang T, et al. Materials Science and Technology,2017,33(1),84.
57 Fu C T, Yinling W, Chu X W, et al. Journal of Nuclear Materials,2017,497,76.
58 Ren W, Muralidharan G, Wilson D F, et al.In: ASME 2011 Pressure Vessels and Piping Conference. American,2011,pp.725.
59 Yang C, Muránsky O, Zhu H, et al. Materials & Design,2017,113,223.
60 Nunes V M B, Queirós C S, Lourenco M J V, et al. Applied Energy,2016,183,603.
61 Zong G, Zhang Z B, Sun J H, et al. Journal of Fluorine Chemistry,2017,197,134.
62 Olander D. Journal of Nuclear Materials,2002,300(2-3),270.
63 Cheng W J, Sellers R S, Anderson M H, et al. Nuclear Technology,2013,183(2),248.
64 Olson L. Transactions of the American Nuclear Society,2015,110,523.
65 Liu Y H, Yang C, Lu Y L, et al. Chinese Journal of Rare Metals,2015,39(10),865(in Chinese).
刘艳红,杨超,陆燕玲,等.稀有金属,2015,39(10),865.
66 Muralidharan G, Wilson D F, Walker L R, et al. Cladding alloys for fluoride salt compatibility,Oak Ridge National Laboratory,2011.
67 Zhu H M, Li B C, Chen M H, et al. Coatings,2018,8,322.
68 Zhu H M, Chen M H, Tang Z F, et al. Rare Metal Materials and Engineering,2018(9),2767(in Chinese).
朱红梅,陈明慧,唐忠锋,等.稀有金属材料与工程,2018(9),2767.
69 Farmer J C. Lawrence Livermore National Laboratory,2008,1,407386.
70 Watanabe T, Kondo M, Nagasaka T, et al. Journal of Plasma and Fusion Research SERIES,2010,9,342.
71 Liu T, Dong J S, Xie G, et al. Acta Metallurgica Sinica,2015,51(9),1059(in Chinese).
刘涛,董加胜,谢光,等.金属学报,2015,51(9),1059.
72 Zhu H M, Li B C, Chen M H, et al. Journal of Fluorine Chemistry,2018,213,80.
73 Brupbacher M C, Zhang D, Buchta W M, et al. Journal of Nuclear Materials,2015,461,215.
74 He X, Song J, Tan J, et al. Journal of Nuclear Materials,2014,448(1-3),1.
75 Wang Y, Tang Z F, Fu Y, et al. Ceramics International,2015,41(10),12996.
76 Gu Y, Liu J X, Wang Y, et al. Journal of the European Ceramic Society,2017,37(7),2575.
77 Yang X, Zhang D, Liu M, et al. Corrosion Science,2016,109,62.
78 Wang H, Feng Q, Wang Z, et al. Corrosion Science,2017,124,131.
79 Yang X, Liu M, Gao Y, et al. Corrosion Science,2016,103,165.
80 Xue W, Yang X, Qiu J, et al. Corrosion Science,2017,114,96.