4.7 Article

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

Journal

JOURNAL OF NUCLEAR MATERIALS
Volume 510, Issue -, Pages 421-430

Publisher

ELSEVIER
DOI: 10.1016/j.jnucmat.2018.08.031

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Funding

  1. Office of Science, of the U.S. Department of Energy [DE-AC02-06CH11357]
  2. DOE, Office of Nuclear Energy, under DOE Idaho Operations Office, Nuclear Science User Facilities [DE-AC07-051D14517]
  3. DOE, Office of Science, Office of Basic Energy Sciences [DE-AC02-06CH11357]

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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 degrees 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. The similar microstructural evolution and irradiation hardening behavior between the HEAs and 316H indicate that, at low temperatures (<= 300 degrees C), the irradiation damage of fcc alloys is not sensitive to compositional variation and configurational entropy. Published by Elsevier B.V.

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