Irradiation effects in high entropy alloys and 316H stainless steel at 300 °C

Chen, Wei -Ying; Liu, Xiang; Chen, Yiren; Yeh, Jien -Wei; Tseng, Ko -Kai; Natesan, Krishnamurti

doi:10.1016/j.jnucmat.2018.08.031

Title: Irradiation effects in high entropy alloys and 316H stainless steel at 300 °C

Journal Article · Fri Aug 17 00:00:00 EDT 2018 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2018.08.031· OSTI ID:1487144

^[1];

^[2]; Chen, Yiren ^[1]; Yeh, Jien -Wei ^[3]; Tseng, Ko -Kai ^[3]; Natesan, Krishnamurti ^[1]

Argonne National Lab. (ANL), Lemont, IL (United States)
Univ. of Illinois, Urbana-Champaign, IL (United States)
National Tsing Hua Univ., Hsing-Chu (Taiwan)

High entropy alloys (HEAs) have been considered for applications in nuclear reactors due to their promising mechanical properties, corrosion and radiation resistance. It has been suggested that sluggish diffusion kinetics and lattice distortion of HEAs can enhance the annihilation of irradiation-induced defects, giving rise to a higher degree of tolerance to irradiation damage. In order to understand the irradiation effects in HEAs and to demonstrate their potential advantages over conventional austenitic stainless steels (SS), we performed in-situ ion irradiation experiments with 1 MeV krypton at 300 °C on two HEAs and a 316H SS under an identical irradiation condition. The irradiation introduced a high density of dislocation loops in all materials, and the microstructural evolution as a function of dose was similar for HEAs and 316H SS. Nanoindentation tests showed that the degree of irradiation hardening was also comparable between them. Furthermore, the similar microstructural evolution and irradiation hardening behavior between the HEAs and 316H indicate that, at low temperatures (≤300 °C), the irradiation damage of fcc alloys is not sensitive to compositional variation and configurational entropy.

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Research Organization:: Argonne National Lab. (ANL), Argonne, IL (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE); USDOE Office of Science (SC), Basic Energy Sciences (BES)

Grant/Contract Number:: AC02-06CH11357; AC07-051D14517

OSTI ID:: 1487144

Alternate ID(s):: OSTI ID: 1691651

Journal Information:: Journal of Nuclear Materials, Vol. 510, Issue C; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 39 works

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Effects of Al and Ti Additions on Irradiation Behavior of FeMnNiCr Multi-Principal-Element Alloy Hoffman, Andrew; He, Li; Luebbe, Matthew JOM, Vol. 72, Issue 1 https://doi.org/10.1007/s11837-019-03871-4	journal	October 2019
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