Fig. 1. Schematic diagram of spark plasma sintering (SPS) device.

Fig. 2. Damage profiles of self-ion implantation calculated by SRIM mode.

Fig. 3. Nanoindentation measured load displacement curves for pure tungsten and rolled W–K before and after irradiation.

Fig. 4. Hardness versus displacement for (a) rolled W–K and (b) pure W, showing an increase in hardness after self-ion irradiation.

Fig. 5. Hardness decreasing with displacement increasing for rolled W–K and pure W after self-ion implanted.

Fig. 6. Load–diaplacement² (P–δ²) curves for (a) pure W and (c) rolled W–K, unirradiated and irradiated. Gradient (K) of P–δ² lines (b) in panel (a) and (d) in panel (c) versus displacement.

Fig. 7. TEM images of dislocation loops in pure W and rolled W–K irradiated to 11.5-dpa damage (TEM bright field images): (a) unirradiated W–K; (b) 11.5-dpa region of rolled W–K; (c) DAR of rolled W–K; (d) 11.5-dpa region of pure W; (e) DAR of pure W. All images have the same scale bar of 100 nm. Red arrow points to top surface of sample, and white box highlighting area enlarged shows dislocation loops of around 15 nm in size.

Fig. 8. (a) Surface morphology of pure W unirradiated. (b) Surface morphology of pure W irradiated. (c) Surface morphology of rolled W–K unirradiated. (d) Surface morphology of rolled W–K irradiated.

Fig. 9. (a) Elasticity moduli of pure tungsten and rolled W–K alloy samples. (b) XRD spectra of tungsten self-ions irradiated samples with black line representing the pure tungsten after being irradiated, red line the pure tungsten before being irradiated, blue line the W–K alloy after being irradiated, and green line the W–K alloy before being irradiated.