The permeation of tritium through the cooling pipes is one of the critical issues in the design of the Pb-17Li water-cooled blanket for the DEMO reactor. Aluminised coatings on the surfaces in contact with the Pb-17Li can significantly reduce the permeation rate through the steel and the tritium inventory in the blanket. A series of tests was conducted in order to verify the behaviour of these coatings in the presence of thermomechanical fatigue and in the Pb-17Li environment. The behaviour of the coatings, which sustained over one thousand thermal cycles in a temperature range of 260-320°C and were subjected to an additional mechanical stress of 100 MPa, was satisfactory. The aluminised surfaces were found to be compatible with the breeder and no appreciable embrittlement attributable to the thermomechanical cycling was noted. © 1994.
All Science Journal Classification (ASJC) codes
- Electronic, Optical and Magnetic Materials
Benamati, G., Elmi, N., & Agostini, M. (1994). Thermomechanical cycling tests of coated AISI 316L in Pb17Li. Journal of Nuclear Materials, 212-215(PART B), 1557 - 1560. https://doi.org/10.1016/0022-3115(94)91089-8