Mechanical behavior of additively manufactured and wrought 316L stainless steels before and after neutron irradiation

Fabrication of nuclear reactor components using additive manufacturing (AM) methods is now a practical option since the AM technologies have advanced to allow for building of complex parts with high quality materials. To assess the mechanical performance of printed components in reactor-relevant con...

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Veröffentlicht in:	Journal of nuclear materials 2021-05, Vol.548, p.152849, Article 152849
Hauptverfasser:	Byun, T.S., Garrison, B.E., McAlister, M.R., Chen, X., Gussev, M.N., Lach, T.G., Coq, A. Le, Linton, K., Joslin, C.B., Carver, J.K., List, F.A., Dehoff, R.R., Terrani, K.A.
Format:	Artikel
Sprache:	eng
Schlagworte:	Additive manufacturing Additively manufactured 316L stainless steels Annealing Ductility Ductility tests Fabrication Heat treatment Heat treatments Irradiation Irradiation hardening and softening Irradiation-induced ductilization MATERIALS SCIENCE Mechanical properties Mechanical tests Necking Neutron flux Neutron irradiation Nuclear reactor components Nuclear reactors Post-build heat treatment Post-irradiation Quality assessment Reactors Stainless steel Stainless steels Temperature Tensile tests
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