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Title: Characterisation of radiation damage in W and W-based alloys from 2MeV self-ion near-bulk implantations

Journal Article · · Acta Materialia
 [1];  [2];  [3];  [4];  [1]
  1. Univ. of Oxford (United Kingdom). Dept. of Materials; Culham Science Centre, Abingdon (United Kingdom). Culham Centre for Fusion Energy (CCFE)
  2. Univ. of Oxford (United Kingdom). Trinity College
  3. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
  4. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

We report that the displacement damage induced in W and W-5 wt.% Re and W-5 wt.% Ta alloys by 2 MeV W+ irradiation to doses 3.3 x 1017 - 2.5 x 1019 W+/m2 at temperatures ranging from 300 to 750 °C has been characterised by transmission electron microscopy. An automated sizing and counting approach based on Image J (a Java-based image processing programme developed at the National Institutes of Health) [1] has been performed for all near-bulk irradiation data. In all cases the damage comprised dislocation loops, mostly of interstitial type, with Burgers vectors b = 1/2 < 111 > (>60%) and b = (1 00). The diameters of loops did not exceed 20 nm with most being ≤ = 6 nm diameter. The loop number density varied between 1022 and 1023 loops/m3. With increasing irradiation temperature, the loop size distributions shifted towards larger sizes, and there was a substantial decrease in loop number densities. The damage microstructure was less sensitive to dose than to temperature. Under the same irradiation conditions, loop number densities in the W-Re and W-Ta alloys were higher than in pure W but loops were smaller. In grains with normals close to z = < 001 >, loop strings developed in pure W at temperatures ≥ = 500 °C and doses ≥= 1.2 dpa, but such strings were not observed in the W-Re or W-Ta alloys. However, in other grain orientations complex structures appeared in all materials and dense dislocation networks formed at higher doses.

Research Organization:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Basic Energy Sciences (BES); USDOE National Nuclear Security Administration (NNSA)
Contributing Organization:
Univ. of Oxford (United Kingdom)
Grant/Contract Number:
AC04-94AL85000; AC05-00OR22725; EP/H018921/1
OSTI ID:
1184999
Alternate ID(s):
OSTI ID: 1261438; OSTI ID: 1432125
Report Number(s):
SAND-2014-20338J; 547696
Journal Information:
Acta Materialia, Vol. 92, Issue C; ISSN 1359-6454
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 132 works
Citation information provided by
Web of Science

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Cited By (13)

Ab initio scaling laws for the formation energy of nanosized interstitial defect clusters in iron, tungsten, and vanadium journal July 2016
TEM studies of 1 MeV Fe + ion-irradiated W alloys by wet chemical method: high-temperature annealing and deuterium retention journal November 2018
Study of irradiation induced surface pattern and structural changes in Inconel 718 alloy journal May 2018
Interaction of carbon with microstructural defects in a W-Re matrix: An ab initio assessment journal August 2019
Dislocation loop and tangle evolution of peak damage region in tungsten irradiated by heavy ion and deuterium plasma journal February 2020
Nanoscale imaging of the full strain tensor of specific dislocations extracted from a bulk sample journal January 2020
Radiation damage in tungsten from cascade overlap with voids and vacancy clusters journal July 2019
The Formation of Microcrystal in Helium Ion Irradiated Aluminum Alloy journal August 2019
Collision cascades overlapping with self-interstitial defect clusters in Fe and W journal April 2019
Effect of He-appm/DPA ratio on the damage microstructure of tungsten journal January 2016
Nano-scale imaging of the full strain tensor of specific dislocations extracted from a bulk sample text January 2019
3D reconstruction of the spatial distribution of dislocation loops using a triangulation approach preprint January 2018
Non-destructive study of collision cascade damage in self-ion irradiated tungsten using HR-EBSD and ECCI text January 2020

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