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Irradiation responses and defect behavior of single-phase concentrated solid solution alloys

Published online by Cambridge University Press:  10 September 2018

Tengfei Yang ,
Congyi Li ,
Steven J. Zinkle ,
Shijun Zhao ,
Hongbin Bei Open the ORCID record for Hongbin Bei [Opens in a new window]  and
Yanwen Zhang
Tengfei Yang
Affiliation:
Department of Nuclear Engineering, University of Tennessee, Knoxville, Tennessee 37996, USA
Congyi Li
Affiliation:
Department of Nuclear Engineering, University of Tennessee, Knoxville, Tennessee 37996, USA
Steven J. Zinkle*
Affiliation:
Department of Nuclear Engineering, University of Tennessee, Knoxville, Tennessee 37996, USA; and Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831, USA
Shijun Zhao
Affiliation:
Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831, USA
Hongbin Bei
Affiliation:
Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831, USA
Yanwen Zhang
Affiliation:
Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831, USA; and Department of Nuclear Engineering, University of Tennessee, Knoxville, Tennessee 37996, USA
*
a)Address all correspondence to this author. e-mail: szinkle@utk.edu
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Abstract

Single-phase concentrated solid solution alloys (SP-CSAs) are newly emerging advanced structural materials, which are defined as multiprincipal element solid solutions. SP-CSAs with more than four components in equimolar or near-equimolar ratios are also referred to as high-entropy alloys due to their high configurational entropy. SP-CSAs are potential structural materials in advanced nuclear energy systems due to their attractive mechanical properties. Therefore many investigations have been carried out to study the irradiation-induced structural damage and defect behavior in SP-CSAs. This paper reviews recent experimental results on the irradiation responses of various SP-CSAs, focusing on the accumulation of irradiation-induced structural damage, void swelling resistance, and solute segregation behavior. In addition, the characteristic defect behavior in SP-CSAs derived from ab initio and molecular dynamics simulations, as well as the challenges in the applications of SP-CSAs for the nuclear energy systems are briefly discussed.

Keywords

nuclear materialsmicrostructuredefects

Information

Type
Invited Review
Information
Journal of Materials Research , Volume 33 , Issue 19: Focus Issue: Fundamental Understanding and Applications of High-Entropy Alloys , 14 October 2018 , pp. 3077 - 3091
Copyright
Copyright © Materials Research Society 2018 

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Footnotes

b)

These authors contributed equally to this work.

This section of Journal of Materials Research is reserved for papers that are reviews of literature in a given area.

References

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