TY - JOUR
T1 - A promising new class of irradiation tolerant materials
T2 - Ti2ZrHfV0.5Mo0.2 high-entropy alloy
AU - Lu, Yiping
AU - Huang, Hefei
AU - Gao, Xuzhou
AU - Ren, Cuilan
AU - Gao, Jie
AU - Zhang, Huanzhi
AU - Zheng, Shijian
AU - Jin, Qianqian
AU - Zhao, Yonghao
AU - Lu, Chenyang
AU - Wang, Tongmin
AU - Li, Tingju
N1 - Publisher Copyright:
© 2018
PY - 2019/3
Y1 - 2019/3
N2 - Recently, high-entropy alloys (HEAs) or multi-principal-element alloys with unprecedented physical, chemical, and mechanical properties, have been considered as candidate materials used in advanced reactors due to their promising irradiation resistant behavior. Here, we report a new single-phase body-centered cubic (BCC) structured Ti2ZrHfV0.5Mo0.2 HEA possessing excellent irradiation resistance, i.e., scarcely irradiation hardening and abnormal lattice constant reduction after helium-ion irradiation, which is completely different from conventional alloys. This is the first time to report the abnormal XRD phenomenon of metallic alloys and almost no hardening after irradiation. These excellent properties make it to be a potential candidate material used as core components in next-generation nuclear reactors. The particular irradiation tolerance derives from high density lattice vacancies/defects.
AB - Recently, high-entropy alloys (HEAs) or multi-principal-element alloys with unprecedented physical, chemical, and mechanical properties, have been considered as candidate materials used in advanced reactors due to their promising irradiation resistant behavior. Here, we report a new single-phase body-centered cubic (BCC) structured Ti2ZrHfV0.5Mo0.2 HEA possessing excellent irradiation resistance, i.e., scarcely irradiation hardening and abnormal lattice constant reduction after helium-ion irradiation, which is completely different from conventional alloys. This is the first time to report the abnormal XRD phenomenon of metallic alloys and almost no hardening after irradiation. These excellent properties make it to be a potential candidate material used as core components in next-generation nuclear reactors. The particular irradiation tolerance derives from high density lattice vacancies/defects.
KW - Defects evolution
KW - High-entropy alloy
KW - Irradiation resistance
KW - Microstructural characterization
UR - https://www.scopus.com/pages/publications/85057868289
U2 - 10.1016/j.jmst.2018.09.034
DO - 10.1016/j.jmst.2018.09.034
M3 - 文章
AN - SCOPUS:85057868289
SN - 1005-0302
VL - 35
SP - 369
EP - 373
JO - Journal of Materials Science and Technology
JF - Journal of Materials Science and Technology
IS - 3
ER -