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

Abstract

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.

Authors:

Chen, Wei -Ying  ^[1];

• Search DOE PAGES for author "Chen, Wei -Ying"
• Search DOE PAGES for ORCID "0000-0002-6583-4204"

Liu, Xiang  ^[2];

• Search DOE PAGES for author "Liu, Xiang"
• Search DOE PAGES for ORCID "0000-0002-2634-1888"

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

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+ Show Author Affiliations

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

Publication Date:

Fri Aug 17 00:00:00 EDT 2018

Research Org.:

Argonne National Lab. (ANL), Argonne, IL (United States)

Sponsoring Org.:

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

OSTI Identifier:

1487144

Alternate Identifier(s):

OSTI ID: 1691651

Grant/Contract Number:  

AC02-06CH11357; AC07-051D14517

Resource Type:

Accepted Manuscript

Journal Name:

Journal of Nuclear Materials

Additional Journal Information:

Journal Volume: 510; Journal Issue: C; Journal ID: ISSN 0022-3115

Publisher:

Elsevier

Country of Publication:

United States

Language:

English

Subject:

36 MATERIALS SCIENCE; TEM; high entropy alloys; in-situ irradiation; irradiation damage; microstructure