Irradiation effects on Al0.3CoCrFeNi and CoCrMnFeNi high-entropy alloys, and 316H stainless steel at 500 °C

被引:34
作者
Chen, Wei-Ying [1 ]
Kirk, Marquis A. [1 ]
Hashimoto, Naoyuki [2 ]
Yeh, Jien-Wei [3 ]
Liu, Xiang [4 ]
Chen, Yiren [1 ]
机构
[1] Argonne Natl Lab, Lemont, IL 60439 USA
[2] Hokkaido Univ, Sapporo, Hokkaido, Japan
[3] Natl Tsing Hua Univ, Hsinchu, Taiwan
[4] Idaho Natl Lab, Idaho Falls, ID USA
关键词
RADIATION-INDUCED SEGREGATION; SOLID-SOLUTION; DEFECT EVOLUTION; DISLOCATION LOOP; ION-IRRADIATION; DAMAGE; NI; CARBON; MICROSTRUCTURE; STABILITY;
D O I
10.1016/j.jnucmat.2020.152324
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
To evaluate the potential of high entropy alloys (HEAs) for nuclear applications, two HEAs, Al0.3CoCrFeNi and CoCrFeMnNi, and a conventional Type 316H stainless steel (SS) were irradiated with 1 MeV krypton ions at 500 degrees C up to 1 dpa, and examined in-situ with a transmission electron microscope (TEM). After irradiation, a high density of ordered L1(2) nanoparticles was observed in Al0.3CoCrFeNi. In contrast, no phase transformation was observed in CoCrFeMnNi and 316H SS. In the thin foil regions of TEM samples, stacking-fault tetrahedra were observed in the HEAs. In the thick foil regions, interstitial dislocation loops were observed for all alloys, and the areal loop density increased linearly with foil thickness. The Al0.3CoCrFeNi had the largest loop size (the lowest density), followed by the CoCrFeMnNi and then the 316H SS. The higher loop nucleation rate in the 316H SS was attributed to carbon content. The degree of irradiation hardening was slightly lower for the HEAs than for the 316H SS, which is a promising sign for the nuclear application of HEAs at high temperatures. Published by Elsevier B.V.
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页数:13
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