Study on the corrosion behavior of austenitic stainless 15-15Ti for nuclear fuel cladding in lead-bismuth eutectic alloy with oxygen control. Issue 1 (1st December 2022)

• Record Type: Journal Article
• Authors: Sun, Yulin; Yuan, Ganfeng; Wang, Da; Ma, Xianfeng; Liang, Yuqiang; Zeng, Jun; Ye, Huanmin; Liu, Sirui; Xiao, Changquan; Hu, Yanying
• Is Part Of: Journal of physics. Volume 2393 Issue 1(2022)
• Publication Date: 2022-12-01
• Subjects: Physics -- Congresses; 530.5
• DOI: 10.1088/1742-6596/2393/1/012018
• Languages: English
• ISSNs: 1742-6588

Abstract

Abstract: The austenitic stainless steel 15-15Ti is one of the main candidate materials for the fuel cladding of the Lead-cooled Fast Reactor (LFR) due to its outstanding irradiation resistance and mechanical properties at high temperatures. The study of the corrosion behavior of 15-15Ti in LBE can help further investigate the service performance in a reactor. In this study, the static LBE corrosion of 15−15Ti was carried out for 1000 h at the temperature of 550°C and the oxygen concentration of 5×10 −7 wt%. The samples were analyzed by Scanning Electron Microscope (SEM), Energy Dispersive X-ray Spectroscopy (EDS), and X-ray Diffraction (XRD). The results showed that 15-15Ti was oxidized and formed a duplex oxide film. The inner oxide film is continuous and the main component is FeCr2 O4 . The outer oxide film is composed of Fe3 O4 . The Fe3 O4 oxides are loose and they could fall off from the surface.