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.
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.