Page 90 - 《摩擦学学报》2020年第4期

500 摩 擦 学 学 报 第 40 卷

要更为深入细致的研究. 而对于润滑材料，在实现宽 [ 6 ] Chivers T C. Nuclear tribology: a personal perspective[J]. Tribology
温域条件下连续润滑设计的同时 [69-70] ，需要考虑Ag、 International, 1986, 19(5): 225–233. doi: 10.1016/0301-
679X(86)90001-0.
Gd、In、B和Mo等常用润滑剂在堆内不同位置使用限
[ 7 ] Zhou Mingsheng, Tian Minbo, Dai Xingjian. Nuclear materials and
制，减少中子活性元素引入. 现阶段反应堆通过延长
applications[M]. Beijing: Tsinghua University Press, 2017(in
运行寿命提高核电运行经济性，按照40年使用寿命计
Chinese) [周明胜, 田民波, 戴兴建. 核材料与应用[M]. 北京: 清华
算，对于堆内服役材料其承受的中子辐照剂量将达到 大学出版社, 2017].
22
2
6×10 n/m ，对应辐照损伤接近100 dpa，如此高剂量 [ 8 ] Blau P J. A multi-stage wear model for grid-to-rod fretting of
辐照下材料肿胀、脆化等性能变化在所难免，这对固 nuclear fuel rods[J]. Wear, 2014, 313(1-2): 89–96. doi: 10.1016/j.wear.
体润滑材料的结构成分设计与制备提出了巨大的挑 2014.02.016.
战. 近年抗辐照结构材料研究表明，材料中的表面、界 [ 9 ] K im, Kyu-Tae. Applicability of out-of-pile fretting wear tests to in-
reactor fretting wear-induced failure time prediction[J]. Journal of
面以及异质相边界等均可以有效吸收辐照引起的缺
Nuclear Materials, 2013, 433(1-3): 364–371. doi: 10.1016/j.jnucmat.
陷，进而可以有效缓解材料的辐照损伤积累，包括氧
2012.10.018.
化物弥散增强、多层以及纳米晶等结构材料抗辐照设 [10] Lee Y H, Kim H K. Fretting wear behavior of a nuclear fuel rod
[71]
计成功经验或许能为我们提供参考 . under a simulated primary coolant condition[J]. Wear, 2013, 301(1-
由于磁约束聚变堆利用高真空实现高温、高热及 2): 569–574. doi: 10.1016/j.wear.2013.01.067.
高密度等离子体在磁场中的约束和控制，因此其润滑 [11] Lee Y H, Kim H K, Jung Y H. Effect of impact frequency on the
需求与裂变堆相比具有特殊性. 诸多应用于航天系统 wear behavior of spring-supported tubes in room and high
temperature distilled water[J]. Wear, 2005, 259(s 1-6): 329–336.
的润滑材料与技术对解决磁约束聚变堆润滑问题具
[12] Han J G, Lee J S, Choi B H, et al. Wear and fretting wear behaviour
有参考意义. 未来聚变堆高效率运行离不开遥操作技
of ion-implanted Zircaloy-4[J]. Surface & Coatings Technology,
术，中国聚变工程实验堆CFETR设计了包括内部破损 1996, 83(1-3): 307–312.
部件维修、偏滤器维修/更换、包层结构拆卸更换以及 [13] Qu J, Cooley K M, Shaw A H, et al. Assessment of wear coefficients
热室转运维护等遥操作技术，利用远程机器人/机械臂 of nuclear zirconium claddings without and with pre-oxidation[J].
操控提高装置运转效率. 这些运动机构工作环境多为 Wear, 2016, 356-357: 17–22. doi: 10.1016/j.wear.2016.02.020.
真空、高低温交变、真空/大气交变、重载以及高能中 [14] Jiang Haixia, Duan Zewen, Zhang BeiBei, et al. Wear behavior of
zirconium-4 alloy after different irradiation damage level[J]. Applied
子辐照等苛刻环境，对于固体润滑材料及技术，在借
Surface Science, 2020, 509: 145373. doi: 10.1016/j.apsusc.2020.
鉴一些应用于航天系统成熟润滑材料的基础上，需要
145373.
考虑环境交变对润滑材料服役行为影响，同时聚变产 [15] Jiang Haixia, Duan Zewen, Zhao Xiaoyu, et al. Influence of ions
生的14 MeV中子对服役材料结构与性能的影响也需 irradiation on the microstructural evolution, mechanical and
要引起足够重视. tribological properties of Zr-4 alloy[J]. Applied Surface Science,
2019, 498: 143821. doi: 10.1016/j.apsusc.2019.143821.
参 考 文 献
[16] Yan C, Wang R, Wang Y, et al. Effects of ion irradiation on
[ 1 ] Su Gang. The “three steps development strategy” of China nuclear microstructure and properties of zirconium alloys-a review[J].
power science and technology[J]. Science & Technology Review, Nuclear Engineering & Technology, 2015, 47(3): 323–331.
2016, 34(15): 33–41 (in Chinese) [苏罡. 中国核能科技“三步走”发 [17] Tupin M, Verlet R, Wolski K, et al. Understanding of corrosion
展战略的思考[J]. 科技导报, 2016, 34(15): 33–41]. mechanisms after irradiation: Effect of ion irradiation of the oxide
[ 2 ] Li Jiangang. The status and progress of tokamak research[J]. layers on the corrosion rate of M5[J]. Zirconium in the Nuclear
Physics, 2016, 45(2): 88–97 (in Chinese) [李建刚. 托卡马克研究的 Industry: 18th International Symposium, 2018.
现状及发展[J]. 物理, 2016, 45(2): 88–97]. doi: 10.7693/wl20160203. [18] Bai Xinde, Wang Sheguan, He Jinghao, et al. Effects of irradiation
[ 3 ] Wan Yuanxi, Li Jiangang, Liu Yong, et al. Overview of the present in nuclear reactors on corrosion behavior of zircaloys[J]. Chinese
progress and activities on the CFETR[J]. Nuclear Fusion, 2017, Journal of Nuclear Science and Engineering, 1996, (3): 243–249,
57(10): 102009. 1–102009. 17. 255 (in Chinese) [白新德, 王社管, 何敬浩, 等. 辐照对堆用锆合金
[ 4 ] Zinkle S J, Was G S. Materials challenges in nuclear energy[J]. Acta 腐蚀行为的影响[J]. 核科学与工程, 1996, (3): 243–249, 255].
Materialia, 2013, 61: 735–758. doi: 10.1016/j.actamat.2012.11.004. [19] Ta ng, Chongchong, Steinbrueck, et al. Deposition, characterization
[ 5 ] Knaster J, Moeslang A, Muroga T. Materials research for fusion[J]. and high-temperature steam oxidation behavior of single-phase
Nature Physics, 2016, 12: 424–434. doi: 10.1038/nphys3735. Ti2AlC-coated Zircaloy-4[J]. Corrosion Science, 2018, 135: 87–98.