高熵合金:面向聚变堆抗辐照损伤的新型候选材料

doi:10.11896/cldb.20050032

Abstract
Figure/Table
References
Related Citation (5)

Download:

Full Text ( PDF ) (8014KB)
Export: BibTeX | EndNote (RIS)

Abstract With the development of nuclear fusion technology, the irradiation damages of materials has gained increasing attention as the vital issues for the restriction of the development of nuclear fusion. During the operation of fusion reactors, the materials are confronted with series of extreme operating conditions, including high temperature, the sputtering of high-density plasma, erosion, neutron irradiation, etc., which requires that the materials have fine characters such as good mechanical properties, neutron irradiation resistance, plasma sputtering resistance and corrosion resistance, etc. Lately, high entropy alloys (HEAs) have been gradually devised as a new irradiation-resistant candidate for fusion reactors materials, and the evaluation of irradiation resistance and the irradiation damage mechanism both require in-depth researches. HEAs are a new concept of alloy design, which forms high-thermostability solid solution phase by high entropy and low diffusivity of multi-component alloy itself. The characters of HEAs are distinguished from conventional alloys, including high entropy effect, high lattice distortion, sluggish diffusion effect and ‘cocktail’ effect, which lead to the high strength and hardness, corrosion resistance, high temperature softening resistance, excellent soft magnetic properties of HEAs. The present researches of irradiation damage of HEAs are mainly conducted by ion irradiation and it is focused on the evolution of dislocation loops, He bubbles and phase stability. It is found that the formation of dislocation loops and He bubbles of HEAs under ion irradiation has been suppressed evidently, which may be ascribed that the high lattice distortion acts as the traps to absorb the irradiation damages, such as vacancies and He atoms, thus relieve the irradiation damages. In addition, towards the operating condition of the fusion plants at high temperature, irradiation-resistant refractory HEAs have been gradually developed, which mainly utilize the high melting point elements as main compositions, such as V, Hf, Ta, W, etc. This paper introduces the research states and progresses of irradiation damages in HEAs, including the evolution of dislocation loops, He bubbles, the phase stability of matrix and precipitations of HEAs under ion irradiation, the irradiation behavior of HEAs under neutron irradiation, as well as the development and progress of irradiation-resistance refractory HEAs towards fusion reactors. Finally, the research directions in future are prospected so as to supply the reference for the development of irradiation-resistant HEAs towards fusion reactor.

Key words： multi-component alloys high entropy alloys irradiation damages ion irradiation dislocation loops

Published: 02 September 2020

CLC number:

TG139.4

Fund:Scientific and Technological Innovation Programs (STIP) of Higher Education Institutions in Shanxi (2019L0168)

About author:: Xuejiao Wang is the lecture of Taiyuan University of Technology. She received bachelor's degree and doctor's degree of School of Materials Science and Engineering,University of Science and Technology of Beijing in 2013 and 2019, respectively. She has engaged in the strengthening/toughening of high entropy alloys and irradiation study of nuclear materials, and has published 4 pieces of SCI papers.
Junwei Qiao is the professor, doctoral supervisor and sub-decanal of Taiyuan University of Technology. He received doctor's degree of School of Materials Science and Engineering,University of Science and Technology of Beijing in 2015. He has engaged in the special high entropy alloys for structure materials, new type of stainless steel (the effect of TWIP and TRIP), the stren-gthening/toughening of bulk amorphous alloys, the behavior of serrated plastic flow in materials and the behavior of metal under severe condition (including low temperature, high strain rate and ion irradiation). He has published over 120 pieces of SCI papers and 10 pieces of inventions, four of them have been selected as ESI papers. Besides, he has held the post of referees of Scientific Reports, JOM, Progress in Materials Science, Applied Physics Letters, Materials Letters, etc.
Yucheng Wu is the professor and doctoral supervisor of Taiyuan University of Technology, as well as the committee member of the 13^th Standing Committee of the National People' s Congress in Shanxi province. He received engineering bachelor's and master's degree of Hefei University of Technology in 1984 and 1987, respectively, and received science doctor's degree of Chinese Academy of Sciences in 2000. He has engaged in the nuclear fusion materials, the conversion and utilization of coal and the Functional nanomaterials. He has held the post of editors of Journal of Heat Treatment of Materials, China Journal of Nonferrous Metals, Function Materials, etc. He has published over 300 pieces of SCI papers, one piece of high quality textbooks of national level, 12 pieces of monographs and 30 pieces of inventions.

	Service
	E-mail this article
	Add to my bookshelf
	Add to citation manager
	E-mail Alert
	RSS
	Articles by authors
	WANG Xuejiao
	QIAO Junwei
	WU Yucheng

Cite this article:

WANG Xuejiao,QIAO Junwei,WU Yucheng. High Entropy Alloys:the New Irradiation-Resistant Candidate Materials Towards the Fusion Reactors[J]. Materials Reports, 2020, 34(17): 17058-17066.

URL:

http://www.mater-rep.com/EN/10.11896/cldb.20050032 OR http://www.mater-rep.com/EN/Y2020/V34/I17/17058

1 Yang F J. Nuclear physics, Higher Education Press, China, 2008 (in Chinese).
杨福家. 原子核物理, 高等教育出版社, 2008.
2 Guo J K. Fusion reactor material, Chemical Industry Press, China, 2007 (in Chinese).
郝嘉琨.聚变堆材料, 化学工业出版社, 2007.
3 Yang W D. Reactor metallurgy, Atomic Energy Press, China, 2000 (in Chinese).
杨文斗.反应堆材料学, 原子能出版社, 2000.
4 Zinkle S J, Snead L L. Annual Review of Materials Research, 2014, 44(1), 241.
5 Yeh J W, Chen S K, Lin S J, et al. Advanced Engineering Materials, 2004, 6(5), 299.
6 Bao M L, Qiao J W. Progress of materials in China, 2018, 37(4), 264 (in Chinese).
鲍美林,乔珺威. 中国材料进展, 2018, 37(4), 264.
7 Zhang W, Liaw P K, Zhang Y. Science China Materials, 2018, 61(1), 2.
8 Liu Y, Li Y X, Chen X, et al. Materials Review, 2006, 20(4), 4 (in Chinese).
刘源,李言祥,陈祥,等. 材料导报, 2006, 20(4), 4.
9 Li A, Shi J, Xie M. Materials Review A:Review Papers, 2018, 32(2), 461(in Chinese).
李安敏, 史君佐, 谢明款. 材料导报:综述篇, 2018, 32(2), 461.
10 Chen Y Y, Duval T, Hung U D, et al. Corrosion Science, 2005, 47(9), 2257.
11 Senkov O N, Wilks G B, Scott J M, et al. Intermetallics, 2011, 19(5), 698.
12 Kai W, Li C C, Cheng F P, et al. Corrosion Science, 2016, 108, 209.
13 Li Z, Pradeep K G, Deng Y, et al. Nature, 2016, 534(7606), 227.
14 Li Z, Tasan C C, Springer H, et al. Scientific Reports, 2017, 7, 40704.
15 Lei Z, Liu X, Wu Y, et al. Nature, 2018, 563(7732), 546.
16 Yasuda H Y, Miyamoto H, Cho K, et al. Materials Letters, 2017, 199, 120.
17 Wani I S, Bhattacharjee T, Sheikh S, et al. Materials Science and Engineering A, 2016, 675, 99.
18 Yeh J W. JOM, 2013, 65(12), 1759.
19 Huang H, Wu Y, He J, et al. Advanced Materials, 2017, 29(30), 1701678.
20 Zhang Y, Zuo T T, Tang Z, et al. Progress in Materials Science, 2014, 61, 1455.
21 Gludovatz B, Hohenwarter A, Catoor D, et al. Science, 2014, 345(6201), 1153.
22 Nagase T, Anada S, Rack P D, et al. Intermetallics, 2012, 26, 122.
23 Chen W, Ding X, Feng Y, et al. Journal of Materials Science and Technology, 2018, 34(2), 355.
24 Chen D, Tong Y, Wang J, et al. Journal of Nuclear Materials, 2018, 510, 187.
25 Granberg F, Nordlund K, Ullah M W, et al. Physical Review Letters, 2016, 116(13), 135504.
26 Lu C, Yang T, Jin K, et al. Acta Materialia, 2017, 127, 98.
27 Koch L, Granberg F, Brink T, et al. Journal of Applied Physics, 2017, 122(10), 105106.
28 Chen D, Zhao S, Sun J, et al. Journal of Nuclear Materials, 2019, 526, 151747.
29 Shi S, He M R, Jin K, et al. Journal of Nuclear Materials, 2018, 501, 132.
30 Tong Y, Velisa G, Zhao S, et al. Materialia, 2018, 2, 73.
31 Kumar N A P A P K, Li C, Leonard K J J, et al. Acta Materialia, 2016, 113, 230.
32 Yan Z, Liu S, Xia S, et al. Journal of Nuclear Materials, 2018, 505, 200.
33 Lu C, Niu L, Chen N, et al. Nature Communications, 2016, 7, 13564.
34 Lu C, Jin K, Béland L K, et al. Scientific Reports, 2016, 6, 19994.
35 Jin K, Lu C, Wang L M, et al. Scripta Materialia, 2016, 119, 65.
36 Lu C, Yang T N, Jin K, et al. Journal of Nuclear Materials, 2019, 524, 60.
37 Yang T ni, Lu C, Jin K, et al. Journal of Nuclear Materials, 2017, 488, 328.
38 Tunes M A, Le H, Greaves G, et al. Intermetallics, 2019, 110, 106461.
39 Yang L, Ge H, Zhang J, et al. Journal of Materials Science and Technology, 2019, 35(3), 300.
40 Wang Y, Zhang K, Feng Y, et al. Journal of Nuclear Materials, 2019, 527, 151785.
41 Velişa G, Fan Z, Crespillo M L, et al. Journal of Alloys and Compounds, 2020, 832, 154918.
42 Pu G, Lin L, Ang R, et al. Applied Surface Science, 2020, 516, 146129.
43 Nagase T, Anada S, Rack P D, et al. Intermetallics, 2013, 38, 70.
44 Nagase T, Rack P D, Noh J H, et al. Intermetallics, 2015, 59, 32.
45 Kombaiah B, Jin K, Bei H, et al. Materials and Design, 2018, 160, 1208.
46 He M R, Wang S, Shi S, et al. Acta Materialia, 2017, 126, 182.
47 Yang T, Xia S, Guo W, et al. Scripta Materialia, 2018, 144, 31.
48 Yang T, Xia S, Liu S, et al. Scientific Reports, 2016, 6, 32146.
49 Xia S, Gao M C, Yang T, et al. Journal of Nuclear Materials, 2016, 480, 100.
50 Barr C M, Nathaniel J E, Unocic K A, et al. Scripta Materialia, 2018, 156, 80.
51 Li C, Hu X, Yang T, et al. Journal of Nuclear Materials, 2019, 527, 151838.
52 Barron P J, Carruthers A W, Fellowes J W, et al. Scripta Materialia, 2020, 176, 12.
53 Kareer A, Waite J C, Li B, et al. Journal of Nuclear Materials, 2019, 526, 151744.
54 Patel D, Richardson M D, Jim B, et al. Journal of Nuclear Materials, 2020, 531, 152005.
55 Sadeghilaridjani M, Ayyagari A, Muskeri S, et al. Journal of Nuclear Materials, 2020, 529, 151955.
56 Lu Y, Huang H, Gao X, et al. Journal of Materials Science and Technology, 2019, 35(3), 369.