Abstract: In order to study the corrosion behavior of 430 stainless steel (430ss) in flowing Pb-Bi alloy at high temperature, corrosion tests of 430ss were performed in the LBE at 550 ℃ for 200 h, 400 h and 600 h with relative velocity of 2.98 m/s. X-ray diffraction (XRD), scanning electron microscope (SEM) and energy dispersive spectrometry (EDS) were carried out to detect the corrosion characteristics of the surface and cross-section of the etched samples. It is found that a compound containing Fe, Cr and O elements formed on the surface of the corrosion samples. The shape of the compound was irregular firstly, and then, the compound grew gradually to assemble the homogeneous oxide layer. The oxide layer could be classified to an outer oxide layer and an inner oxide layer. The double-layer oxide films were composed of magnetite Fe3O4 outer layer with penetration of Pb-Bi and Fe-Cr spinel (Fe,Cr)3O4 inner layer. The outer oxide layer was porous while the inner one was compact. With the increase of corrosion time (0—600 h), the thickness of oxide layers became thicker gradually. The metal exhibited dissolution-corrosion and oxidation-corrosion during the corrosion process.
1 Rivai A K, Takahashi M. Journal of Nuclear Materials, 2010, 398, 139. 2 Rivai A K, Takahashi M. Journal of Nuclear Materials, 2010, 398 (1-3), 146. 3 Takahashi M, Ishikawa K, Suzuki T, et al. In: 10th International Conference on Nuclear Engineering. Arlington, 2002, pp.607. 4 Zhang J S, Li N. Journal of Nuclear Materials, 2008, 373, 351. 5 Li N. Journal of Nuclear Materials, 2002, 300, 73. 6 Wu Y C, Huang Q Y, Bai Y Q, et al. Nuclear Science and Engineering, 2010, 30 (3), 238 (in Chinese). 吴宜灿, 黄群英, 柏云清,等. 核科学与工程, 2010, 30 (3), 238. 7 Chen G, Lei Y C, Zhu Q, et al. Journal of Nuclear Materials, 2019, 515, 187. 8 Chen G, Lei Y C, Zhu Q, et al. Corrosion, DOI:org/10.5006/3066. 9 Li T Q, Gu J, Lei Y C, et al. Transactions of the China Welding Institution, 2016, 37 (11), 19 (in Chinese). 李天庆, 顾俊, 雷玉成, 等. 焊接学报, 2016, 37 (11),19. 10 Huang F, Lei Y C, Lu C, et al. Welding Technology, 2016, 45 (5), 111 (in Chinese). 黄飞, 雷玉成, 陆超, 等. 焊接技术, 2016, 45 (5), 111. 11 Kurara Y, Futakawa M, Kikuchi K, et al. Journal of Nuclear Materials, 2002, 301, 28. 12 Kurara Y, Futakawa M, Saito S. Journal of Nuclear Materials, 2005, 343 (1), 333. 13 Kurara Y, Futakawa M, Saito S. Journal of Nuclear Materials, 2008, 373 (1-3), 164. 14 Kondo M, Takahashi M, Sawada N, et al. Journal of Nuclear Materials, 2006, 43 (2), 107. 15 Concetta F. Handbook on lead-bismuth eutectic alloy and lead properties, materials compatibility, thermal-hydraulics and technologies, Nuclear Energy Agency, France, 2015. 16 Schroer C, Wedemeyer O, Novotny J, et al. Corrosion Science, 2014, 84, 13. 17 Zhang J S, Li N. Corrosion Science, 2007, 49 (11), 4154. 18 Chen H J, Chen Y, Zhang J S. Progress in Nuclear Energy, 2008, 50 (2), 587.
渝公网安备50019002502923号 版权所有：《材料导报》编辑部
2020, Vol. 34 
