Irradiation damage and swelling of carbon-doped Fe 38 Mn 40 Ni 11 Al 4 Cr 7 high-entropy alloys under heavy ion irradiat
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Irradiation damage and swelling of carbon-doped Fe38Mn40Ni11Al4Cr7 high-entropy alloys under heavy ion irradiation at elevated temperature Shangkun Shen1,3, Feida Chen1,3,*, Xiaobin Tang1,2,*, Guojia Ge1, Jing Gao1, and Zhangjie Sun1 1
Department of Nuclear Science and Technology, Nanjing University of Aeronautics and Astronautics, Nanjing 211106, China Key Laboratory of Nuclear Technology Application and Radiation Protection in Astronautics (Nanjing University of Aeronautics and Astronautics), Ministry of Industry and Information Technology, Nanjing 211106, China 3 Jiangsu Engineering Laboratory of Nuclear Energy Equipment Materials, Nanjing 211106, China 2
Received: 22 June 2020
ABSTRACT
Accepted: 30 July 2020
Interstitial strengthening is one of the main approaches to improving the mechanical properties of high-entropy alloys (HEAs), but its effects on the irradiation resistance of HEAs need further study. Here, we investigated the irradiation-induced defects and swelling of Fe38Mn40Ni11Al4Cr7 HEAs with different carbon contents under 5 MeV Xe23? irradiation at 300 °C and 500 °C. Results show that the irradiation-induced swelling was significantly suppressed as the carbon content increased. Under the observation of TEM, the size of irradiation-induced dislocation loops also decreases with increasing carbon content. By comparing the effects of carbon content at different temperatures on the evolution of defects, the pinning effect of interstitial carbon on irradiationinduced defects of HEAs was proposed and analyzed. Carbon atoms, which are stabilized in the octahedron clearance of HEAs with FCC structure, not only promote the recombination of point defects by enhancing the sluggish diffusion effect of HEAs, but also pin the common 1/3 \111[ faulted loops caused by irradiation. This pinning effect is the main mechanism of interstitial carbon for improving the irradiation resistance of HEAs below 300 °C. In summary, this study provides an essential experimental basis for the irradiation effects of carbon-doped HEAs and strives to reveal the effect of interstitial carbon on irradiation-induced defects at different temperatures.
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https://doi.org/10.1007/s10853-020-05229-7
J Mater Sci
GRAPHICAL ABSTRACT
Introduction Structural materials for nuclear reactor applications are exposed to prolonged irradiation at elevated temperatures, which could cause the swelling [1, 2], hardening [1, 3], and irradiation assisted stress corrosion cracking [4] of materials, thereby endangering the safe and long-term operation of nuclear reactors. According to previous research, high-entropy alloys (HEAs) are considered one of the candidate structural materials for next-generation nuclear reactors due to their superior mechanical properties [5, 6] and good irradiation resistance [7, 8] compared with those of conventional metal materials. The curren
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