Irradiation responses and defect behavior of single-phase concentrated solid solution alloys
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REVIEW This section of Journal of Materials Research is reserved for papers that are reviews of literature in a given area.
Irradiation responses and defect behavior of single-phase concentrated solid solution alloys Tengfei Yangb) and Congyi Lib) Department of Nuclear Engineering, University of Tennessee, Knoxville, Tennessee 37996, USA
Steven J. Zinklea) 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 and Hongbin Bei Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831, USA
Yanwen Zhang 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 (Received 15 April 2018; accepted 24 July 2018)
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.
I. INTRODUCTION
Nuclear power accounts for more than 11% of world electricity production and is a clean energy source with near-zero carbon emission.1,2 On the other hand, the long-term reliability and safety of nuclear power systems depend on the integrity of its structural materials.3 For future advanced fission and fusion reactors, the core structure materials are generally exposed to the aggressive environments, including high temperatures, large time-varying stresses, chemically reactive environments, and intense neutron irradiation.4 All of these attributes place demanding requirements on the structural materials used in advanced reactors. Energetic neutrons produced from nuclear fission or fusion damage the material by inducing significant atomic displacements and creating point defects or defect clusters. In some cases, atoms will be displaced from their initial lattice positions up to 200 times, producing a very high concentration of a)
Address all correspondence to this author. e-mail: [email protected] b) These authors contributed equa
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