Effect of helium bubbles on irradiation hardening of additive manufacturing 316L stainless steel under high temperature He ions irradiation

• Published in: Journal of nuclear materials 2021-07, Vol.550, p.152948, Article 152948
• Main Authors: Fu, Chonglong, Li, Jianjian, Bai, Juju, Li, Ying, Chen, Qian, Lei, Guanhong, Lin, Jun, Zhu, Zhiyong, Meng, Ying
• Format: Article
• Language: English
• Subjects: 316L SS; Additive manufacturing; Austenitic stainless steels; Bubbles; Density; Grain sub boundaries; He bubble; He ions irradiation; Heat resistance; Heat resistant steels; Helium ions; High temperature; Irradiation; Irradiation hardening; Laser beam melting; Mechanical properties; Nanoindentation; Nuclear energy; Nuclear engineering; Nuclear reactors; Stainless steel; Stainless steels
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/j.jnucmat.2021.152948

•SLM 316L SS has a better resistance to irradiation hardening than TM 316L SS under high temperature He ions irradiation.•The number density of He bubbles in TM samples was larger than that in SLM samples, while the diameter was no significant difference.•The difference in the number density of He bubbles might be the main factor causing the different irradiation hardening behavior in two kinds of samples.•The interfaces and intrinsic defects in SLM 316L SS might reduce density of He bubbles and size of dislocation loops effectively. To evaluate the effects of irradiation on additive manufacturing materials which are expected to be applied in advanced nuclear energy systems, selective laser melting 316L stainless steel (SLM 316L SS) and traditionally manufactured 316L stainless steel (TM 316L SS), were irradiated with 500 keV He ions at 700°C, respectively. SEM, TEM and nanoindentation measurements were performed to survey the effects of helium (He) bubbles on the irradiation hardening. It was found that the degree of irradiation hardening of the two materials increased with an increase of ions fluences. The hardening range of SLM 316L SS was 6-47% while that of TM 316L SS was 32-75%. Moreover, the hardening saturation phenomenon was more pronounced in TM 316L SS than in SLM 316L SS. These results suggested that SLM 316L SS owned higher resistance to irradiation hardening than TM 316L SS. TEM observations showed that the density of He bubbles in TM 316L SS was 7.06 × 1023/m3 while that in SLM 316L SS was 3.33 × 1023/m3. Further, the average sizes of bubbles were 2.2 and 2.4 nm, respectively. The differences of the number density might be why SLM 316L SS had a slighter irradiation hardening than TM 316L SS, which was consistent with Orowan model. It was suggested that the numerous intrinsic microstructures such as entangled dislocation network walls and subgrain boundaries in SLM 316L SS could greatly reduce the density of He bubbles. [Display omitted]