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Achieving Radiation Tolerance through Non-Equilibrium Grain Boundary Structures

Journal Article · · Scientific Reports
 [1];  [2];  [2];  [3];  [4];  [4];  [5];  [3];  [2];  [2]
  1. Drexel Univ., Philadelphia, PA (United States). Dept. of Materials Science and Engineering; DOE/OSTI
  2. Drexel Univ., Philadelphia, PA (United States). Dept. of Materials Science and Engineering
  3. Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Center for Integrated Nanotechnologies
  4. Argonne National Lab. (ANL), Argonne, IL (United States); IVEM-Tandem Facility
  5. Los Alamos National Lab. (LANL), Los Alamos, NM (United States). Ion Beam Materials Laboratory, Materials Science and Technology Division
Many methods used to produce nanocrystalline (NC) materials leave behind non-equilibrium grain boundaries (GBs) containing excess free volume and higher energy than their equilibrium counterparts with identical 5 degrees of freedom. Since non-equilibrium GBs have increased amounts of both strain and free volume, these boundaries may act as more efficient sinks for the excess interstitials and vacancies produced in a material under irradiation as compared to equilibrium GBs. The relative sink strengths of equilibrium and non-equilibrium GBs were explored by comparing the behavior of annealed (equilibrium) and as-deposited (non-equilibrium) NC iron films on irradiation. These results were coupled with atomistic simulations to better reveal the underlying processes occurring on timescales too short to capture using in situ TEM. After irradiation, NC iron with non-equilibrium GBs contains both a smaller number density of defect clusters and a smaller average defect cluster size. Simulations showed that excess free volume contribute to a decreased survival rate of point defects in cascades occurring adjacent to the GB and that these boundaries undergo less dramatic changes in structure upon irradiation. These results suggest that non-equilibrium GBs act as more efficient sinks for defects and could be utilized to create more radiation tolerant materials in future.
Research Organization:
Drexel Univ., Philadelphia, PA (United States)
Sponsoring Organization:
USDOE Office of Science (SC)
Grant/Contract Number:
SC0008274
OSTI ID:
1624341
Journal Information:
Scientific Reports, Journal Name: Scientific Reports Journal Issue: 1 Vol. 7; ISSN 2045-2322
Publisher:
Nature Publishing GroupCopyright Statement
Country of Publication:
United States
Language:
English

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Cited By (5)

Outstanding radiation resistance of tungsten-based high-entropy alloys journal March 2019
Modeling Diffusion in Functional Materials: From Density Functional Theory to Artificial Intelligence journal July 2019
Interplay Between Grain Boundaries and Radiation Damage journal March 2019
Improved high temperature radiation damage tolerance in a three-phase ceramic with heterointerfaces journal September 2018
Impact of in situ nanomechanics on physical metallurgy journal June 2019

Figures / Tables (5)


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