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Influence of chemical disorder on energy dissipation and defect evolution in advanced alloys

Published online by Cambridge University Press:  26 August 2016

Yanwen Zhang*
Affiliation:
Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, TN 37831, USA
Ke Jin
Affiliation:
Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, TN 37831, USA
Haizhou Xue
Affiliation:
Department of Materials Science and Engineering, University of Tennessee, Knoxville, TN 37996, USA
Chenyang Lu
Affiliation:
Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI 48109, USA
Raina J. Olsen
Affiliation:
Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, TN 37831, USA
Laurent K. Beland
Affiliation:
Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, TN 37831, USA
Mohammad W. Ullah
Affiliation:
Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, TN 37831, USA
Shijun Zhao
Affiliation:
Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, TN 37831, USA
Hongbin Bei
Affiliation:
Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, TN 37831, USA
Dilpuneet S. Aidhy
Affiliation:
Department of Mechanical Engineering, University of Wyoming, Laramie, WY 82071, USA
German D. Samolyuk
Affiliation:
Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, TN 37831, USA
Lumin Wang
Affiliation:
Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI 48109, USA
Magdalena Caro
Affiliation:
Materials Science and Technology Division, Los Alamos National Laboratory, Los Alamos, NM 87545, USA
Alfredo Caro
Affiliation:
Materials Science and Technology Division, Los Alamos National Laboratory, Los Alamos, NM 87545, USA
G. Malcolm Stocks
Affiliation:
Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, TN 37831, USA
Ben C. Larson
Affiliation:
Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, TN 37831, USA
Ian M. Robertson
Affiliation:
Department of Materials Science and Engineering, University of Wisconsin–Madison, Madison, WI 53706, USA
Alfredo A. Correa
Affiliation:
Physics Division, Lawrence Livermore National Laboratory, Livermore, CA 94550, USA
William J. Weber
Affiliation:
Department of Materials Science and Engineering, University of Tennessee, Knoxville, TN 37996, USA; and Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, TN 37831, USA
*
a) Address all correspondence to this author. e-mail: zhangyl@ornl.gov

Abstract

Historically, alloy development with better radiation performance has been focused on traditional alloys with one or two principal element(s) and minor alloying elements, where enhanced radiation resistance depends on microstructural or nanoscale features to mitigate displacement damage. In sharp contrast to traditional alloys, recent advances of single-phase concentrated solid solution alloys (SP-CSAs) have opened up new frontiers in materials research. In these alloys, a random arrangement of multiple elemental species on a crystalline lattice results in disordered local chemical environments and unique site-to-site lattice distortions. Based on closely integrated computational and experimental studies using a novel set of SP-CSAs in a face-centered cubic structure, we have explicitly demonstrated that increasing chemical disorder can lead to a substantial reduction in electron mean free paths, as well as electrical and thermal conductivity, which results in slower heat dissipation in SP-CSAs. The chemical disorder also has a significant impact on defect evolution under ion irradiation. Considerable improvement in radiation resistance is observed with increasing chemical disorder at electronic and atomic levels. The insights into defect dynamics may provide a basis for understanding elemental effects on evolution of radiation damage in irradiated materials and may inspire new design principles of radiation-tolerant structural alloys for advanced energy systems.

Information

Type
Invited Feature Paper
Copyright
Copyright © Materials Research Society 2016 
Figure 0

FIG. 1. Calculated disorder broadening of electronic energy band or Bloch spectral density function along high symmetry directions. The plots from top to bottom are for Ni, NiCo, NiFe, NiFeCo, NiCoCr, and NiCoFeCr; left side are majority (spin up) and right side are minority (spindown), respectively. Adapted from Refs. 2 and 5.

Figure 1

FIG. 2. The measured electrical resistivity of Ni and SP-CSA. Adapted from Ref. 5.

Figure 2

FIG. 3. Comparison of the momentum transfer calculated from TD-DFT and the adiabatic approximation from Born–Oppenheimer approximation (BOA) for Ni ion in Ni target. The inset is the comparison shown in logarithmic scale.

Figure 3

FIG. 4. Number of Frenkel pairs resulting from cascade simulations of 40 keV recoils in Ni, NiCo, and NiFe. The statistical uncertainty is marked accordingly. Adapted from Ref. 40.

Figure 4

FIG. 5. Irradiation-induced interstitial dislocation loops on {111} planes in pure Ni from (a) a high-resolution high angle annular dark field (HAADF) image, (b) the corresponding inverse fast Fourier transform (IFFT) image (Ref. 39), and (c) from MD simulation.

Figure 5

FIG. 6. Defect clusters in (a) Ni and (b) NiFe, and comparison of the clusters size in (c). NiFe has large number of small clusters compared to Ni (vacancies are shown in blue, and Ni and Fe interstitials in green and pink, respectively). Adapted from Ref. 39.

Figure 6

FIG. 7. The aging of 10 keV cascade debris in Ni generated by MD as simulated using the k-ART. Vacancies are illustrated in red and interstitials in blue. Defect aggregation, annihilation, and reconfiguration are observed.

Figure 7

FIG. 8. Accumulation of point defects in Ni and the two binaries of Ni, Ni0.8Fe0.2 and Ni0.8Cr0.2 as a function of damage dose under cumulative recoil events (5 keV). The lines are curve fit to guide the eye. Insets represent defect cluster formation after 400 recoils (∼0.13 dpa) in Ni (left) and Ni0.8Cr0.2 (right). Vacancies are shown in green and interstitials in blue. Adapted from Ref. 42.

Figure 8

FIG. 9. Irradiation performance of Ni and equiatomic alloys of NiCo and NiFe under 3 MeV Au ion bombardments. (a) and (b) represent disorder profiles in the three crystals upon irradiation to 1 × 1013 and 2 × 1013 Au cm−2, respectively, (c) and (d) are the size distribution of defect clusters in the samples irradiated to 2 × 1013 and 1 × 1014 Au cm−2 determined from TEM observation. Adapted from Refs. 2, 35, and 60.

Figure 9

FIG. 10. Ion channeling backscattering spectra showing different irradiation response in Ni and Ni-containing SP-CSAs. The solid lines are data fit to guide the eye. The irradiation was performed using 1.5 MeV nickel to a fluence of 1 × 1014 cm−2 at room temperature.