Limitations of W and W–1%La2O3 for use as structural materials

Recent divertor designs for future fusion demonstration reactors include dispersion strengthened tungsten as structural material. Their operation temperature window – currently estimated to be between 800 °C and 1200 °C – is restricted by embrittlement on the lower limit. Therefore, standard impact tests have been performed with specimens fabricated from commercial tungsten and W–1%La2O3 rods. Due to the anisotropic microstructure, specimens were oriented parallel to rod axis for optimum Charpy properties. Nevertheless, ductile-to-brittle transition temperatures of just 800 ± 50 °C for tungsten and approximately 950 ± 50 °C for W–1%La2O3 have been determined. But for use as structural material under fusion-specific neutron irradiation, an according alloy should exhibit transition temperatures of 200–400 °C, at least. Therefore, the impact of these results on the use of dispersion strengthened tungsten for divertor structures are discussed in detail.