Material selection and development of corrosion resistant ceramic coatings for nuclear and aerospace applications
FARNHAM M. 1, LIU J. 2, ARMSTRONG D. 2, LYONS J. 1, PRENTICE C. 1, SKILLETT R. 1
1 Archer Technicoat Ltd, High Wycombe, United Kingdom; 2 Oxford University, Oxford, United Kingdom
Pure liquid lithium is a candidate breeding media within tritium breeder blanket (TBB) modules in the next generation of fusion reactor designs. Careful material selection must be undertaken such that materials are compatible with the corrosive environment at temperatures >500°C. Furthermore, these materials should be reasonably compatible with neutron irradiation, act as hydrogen isotope permeation barriers (HIPBs) and be electrically insulating to mitigate pressure drops due to magnetohydrodynamics (MHDs) of flowing metal. Possible structural materials of SiCf/SiC eramic matrix composites (CMCs) and grade T91 steel have limited compatibility with such conditions, therefore protective coatings will be required that are compatible should they be used. A literature review was conducted to identify potentially compatible coating materials and chemical vapour deposition (CVD) processes were developed to deposit coatings of single- and mixed-component oxides. These coatings were applied to representative samples of SiCf/SiC and T91 steel, which were subsequently exposed to static liquid lithium at 500°C. The corrosion test results are discussed with respect to elemental analysis of the samples and possible failure mechanisms associated with the coatings. Many of the coatings developed also show potential within aerospace for use in SiCf/SiC CMCs as steam oxidation and CMAS resistant coatings, with demonstrations of potential applications presented.