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In-situ TEM observation of the response of ultrafine- and nanocrystalline-grained tungsten to extreme irradiation environments

Journal Article · · Scientific Reports
DOI:https://doi.org/10.1038/srep04716· OSTI ID:1624706
 [1];  [2];  [2];  [3];  [4];  [5];  [6]
  1. Purdue Univ., West Lafayette, IN (United States). School of Nuclear Engineering; Purdue Univ., West Lafayette, IN (United States). School of Materials Engineering; Birck Nanotechnology Center, West Lafayette, IN (United States); DOE/OSTI
  2. Univ. of Huddersfield (United Kingdom). School of Computing and Engineering
  3. Purdue Univ., West Lafayette, IN (United States). School of Nuclear Engineering
  4. Purdue Univ., West Lafayette, IN (United States). School of Materials Engineering
  5. Purdue Univ., West Lafayette, IN (United States). Center for Materials Processing and Tribology
  6. Purdue Univ., West Lafayette, IN (United States). School of Nuclear Engineering; Purdue Univ., West Lafayette, IN (United States). School of Materials Engineering; Birck Nanotechnology Center, West Lafayette, IN (United States)
The accumulation of defects, and in particular He bubbles, can have significant implications for the performance of materials exposed to the plasma in magnetic-confinement nuclear fusion reactors. Some of the most promising candidates for deployment into such environments are nanocrystalline materials as the engineering of grain boundary density offers the possibility of tailoring their radiation resistance properties. In order to investigate the microstructural evolution of ultrafine- and nanocrystalline-grained tungsten under conditions similar to those in a reactor, a transmission electron microscopy study with in situ 2 keV He1 ion irradiation at 9506C has been completed. A dynamic and complex evolution in the microstructure was observed including the formation of defect clusters, dislocations and bubbles. Nanocrystalline grains with dimensions less than around 60 nm demonstrated lower bubble density and greater bubble size than larger nanocrystalline (60–100 nm) and ultrafine (100–500 nm) grains. In grains over 100 nm, uniform distributions of bubbles and defects were formed. At higher fluences, large faceted bubbles were observed on the grain boundaries, especially on those of nanocrystalline grains, indicating the important role grain boundaries can play in trapping He and thus in giving rise to the enhanced radiation tolerance of nanocrystalline materials.
Research Organization:
Purdue Univ., West Lafayette, IN (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Basic Energy Sciences (BES). Materials Sciences & Engineering Division
Grant/Contract Number:
SC0004032
OSTI ID:
1624706
Journal Information:
Scientific Reports, Journal Name: Scientific Reports Journal Issue: 1 Vol. 4; ISSN 2045-2322
Publisher:
Nature Publishing GroupCopyright Statement
Country of Publication:
United States
Language:
English

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Effects of zirconium element on the microstructure and deuterium retention of W–Zr/Sc2O3 composites journal September 2016
Effect of high-flux, low-energy He+ ion irradiation on Ta as a plasma-facing material journal December 2016
Asymmetric interaction of point defects and heterophase interfaces in ZrN/TaN multilayered nanofilms journal January 2017
The Role of Grain Size on Neutron Irradiation Response of Nanocrystalline Copper journal March 2016
Enhanced Radiation Tolerance of Tungsten Nanoparticles to He Ion Irradiation journal December 2018
Interplay Between Grain Boundaries and Radiation Damage journal March 2019
Bending mechanical properties of W/TiN/Ta composites with interfacial TiN coatings journal September 2018
Manufacturing of tungsten and tungsten composites for fusion application via different routes journal March 2019
Nanostructured laminar tungsten alloy with improved ductility by surface mechanical attrition treatment journal May 2017
Direct Observation of Sink-Dependent Defect Evolution in Nanocrystalline Iron under Irradiation journal May 2017
Softening due to Grain Boundary Cavity Formation and its Competition with Hardening in Helium Implanted Nanocrystalline Tungsten journal February 2018
IM3D: A parallel Monte Carlo code for efficient simulations of primary radiation displacements and damage in 3D geometry journal December 2015
Alternative Plasma-Facing-Material Concepts for Extreme Plasma-Burning Nuclear Fusion Environments journal October 2019
Grain size threshold for enhanced irradiation resistance in nanocrystalline and ultrafine tungsten journal February 2017
He-ion induced surface morphology change and nanofuzz growth on hot tungsten surfaces journal December 2018
An in situ characterization technique for electron emission behavior under a photo-electric-common-excitation field: study on the vertical few-layer graphene individuals journal August 2019
Effect of He-appm/DPA ratio on the damage microstructure of tungsten journal January 2016
Effect of Zr additions on crystal structures and mechanical properties of binary W–Zr alloys: A first-principles study journal November 2018
On the Structural and Chemical Homogeneity of Spark Plasma Sintered Tungsten journal August 2019

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