A promising new class of irradiation tolerant materials: Ti2ZrHfV0.5Mo0.2 high-entropy alloy

doi:10.1016/j.jmst.2018.09.034

Abstract

Abstract:

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 Ti₂ZrHfV_0.5Mo_0.2 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.

Key words: High-entropy alloy, Irradiation resistance, Microstructural, characterization, Defects evolution

Yiping Lu, Hefei Huang, Xuzhou Gao, Cuilan Ren, Jie Gao, Huanzhi Zhang, Shijian Zheng, Qianqian Jin, Yonghao Zhao, Chenyang Lu, Tongmin Wang, Tingju Li. A promising new class of irradiation tolerant materials: Ti₂ZrHfV_0.5Mo_0.2 high-entropy alloy[J]. J. Mater. Sci. Technol., 2019, 35(3): 369-373.

Figures/Tables 4

Fig. 1. (a) XRD patterns of initial and irradiated Ti2ZrHfV0.5Mo0.2 HEA at ion doses of 5?×?1015, 1?×?1016 and 3?×?1016 ions/cm2, respectively. (b) Variation of lattice parameter versus irradiation doses.

Fig. 2. (a) TEM images of Ti2ZrHfV0.5Mo0.2 HEA at irradiation dose of 3?×?1016 ions/cm2. The maximum density of He bubbles appears at 7.3?μm from the surface. (b-d) Magnified images of regions “A” “B” and “C” in (a) respectively. (e-g) Magnified images at peak damage region of the irradiated samples with ion dose of respectively 5?×?1015, 1?×?1016 and 3?×?1016 ions/cm2.

Fig. 3. (a) Average nanoindentation hardness versus the indentation depth of unirraidated and irradiated Ti2ZrHfV0.5Mo0.2 HEA at ion doses of 5?×?1015, 1?×?1016 and 3?×?1016 ions/cm2, respectively. (b) Positron annihilation experiment of Ti2ZrHfV0.5Mo0.2 HEA and 316L steel.

Fig. 4. A schematic diagram of the He ion being captured in the vacancy defects of Ti2ZrHfV0.5Mo0.2 HEA.

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A promising new class of irradiation tolerant materials: Ti₂ZrHfV_0.5Mo_0.2 high-entropy alloy

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