TY - JOUR
T1 - Heavy ion irradiation response of an additively manufactured 316LN stainless steel
AU - Shang, Zhongxia
AU - Fan, Cuncai
AU - Ding, Jie
AU - Xue, Sichuang
AU - Gabriel, Adam
AU - Shao, Lin
AU - Voisin, Thomas
AU - Wang, Y. Morris
AU - Niu, Tongjun
AU - Li, Jin
AU - de la Rubia, Tomas Diaz
AU - Wang, Haiyan
AU - Zhang, Xinghang
PY - 2021/4/1
Y1 - 2021/4/1
N2 - Additive manufacturing has become an appealing technique to fabricate three-dimensional metallic materials and components for nuclear reactors. However, response of additively manufactured alloys to high-dose heavy ion irradiations at elevated temperatures is still not well understood. Here, an additively manufactured 316LN austenitic stainless steel with high-density solidification cells was irradiated using 3.5 MeV Fe ion to a peak dose of 220 dpa at 450 ˚C. Microscopy studies show a lower Frank loop density and smaller size in the additively manufactured sample compared with its cold worked counterpart, and the cellular structures may largely suppress the formation of perfect loops and dislocation networks and reduce the magnitude of solute segregations comparing with high angle grain boundaries. The present work advances the understanding on the high-temperature irradiation response of additively manufactured steels for nuclear reactor applications.
AB - Additive manufacturing has become an appealing technique to fabricate three-dimensional metallic materials and components for nuclear reactors. However, response of additively manufactured alloys to high-dose heavy ion irradiations at elevated temperatures is still not well understood. Here, an additively manufactured 316LN austenitic stainless steel with high-density solidification cells was irradiated using 3.5 MeV Fe ion to a peak dose of 220 dpa at 450 ˚C. Microscopy studies show a lower Frank loop density and smaller size in the additively manufactured sample compared with its cold worked counterpart, and the cellular structures may largely suppress the formation of perfect loops and dislocation networks and reduce the magnitude of solute segregations comparing with high angle grain boundaries. The present work advances the understanding on the high-temperature irradiation response of additively manufactured steels for nuclear reactor applications.
KW - Additively manufactured 316LN SS
KW - chemical segregation
KW - dislocation loops
KW - heavy ion irradiation
KW - solidification cellular structures
UR - http://www.scopus.com/inward/record.url?scp=85099453446&partnerID=8YFLogxK
UR - https://www.scopus.com/record/pubmetrics.uri?eid=2-s2.0-85099453446&origin=recordpage
U2 - 10.1016/j.jnucmat.2020.152745
DO - 10.1016/j.jnucmat.2020.152745
M3 - RGC 21 - Publication in refereed journal
SN - 0022-3115
VL - 546
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
M1 - 152745
ER -