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Title: High temperature annealing of ion irradiated tungsten

Abstract

In this study, transmission electron microscopy of high temperature annealing of pure tungsten irradiated by self-ions was conducted to elucidate microstructural and defect evolution in temperature ranges relevant to fusion reactor applications (500–1200°C). Bulk isochronal and isothermal annealing of ion irradiated pure tungsten (2 MeV W + ions, 500°C, 1014 W +/cm 2) with temperatures of 800, 950, 1100 and 1400°C, from 0.5 to 8 h, was followed by ex situ characterization of defect size, number density, Burgers vector and nature. Loops with diameters larger than 2–3 nm were considered for detailed analysis, among which all loops had View the MathML source and were predominantly of interstitial nature. In situ annealing experiments from 300 up to 1200°C were also carried out, including dynamic temperature ramp-ups. These confirmed an acceleration of loop loss above 900°C. At different temperatures within this range, dislocations exhibited behaviour such as initial isolated loop hopping followed by large-scale rearrangements into loop chains, coalescence and finally line–loop interactions and widespread absorption by free-surfaces at increasing temperatures. An activation energy for the annealing of dislocation length was obtained, finding E a=1.34±0.2 eV for the 700–1100°C range.

Authors:
 [1];  [2];  [3];  [1];  [4];  [5]
  1. Univ. of Oxford (United Kingdom)
  2. Univ. of Oxford (United Kingdom) ; Culham Science Centre, Abingdon (United Kingdom). Culham Centre for Fusion Energy (CCFE), EURATOM/UKAEA Fusion Association
  3. Shimane Univ., Matsue (Japan); CREST, JST, 7, Gobancho, Chiyoda-ku, Tokyo (Japan)
  4. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  5. Univ. of Oxford (United Kingdom); Culham Science Centre, Abingdon (United Kingdom). Culham Centre for Fusion Energy (CCFE), EURATOM/UKAEA Fusion Association
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE Office of Science (SC)
OSTI Identifier:
1265312
Grant/Contract Number:
AC05-00OR22725
Resource Type:
Journal Article: Accepted Manuscript
Journal Name:
Acta Materialia
Additional Journal Information:
Journal Volume: 90; Journal ID: ISSN 1359-6454
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY; Tungsten; Ion irradiation; Annealing; TEM; Fusion

Citation Formats

Ferroni, Francesco, Yi, Xiaoou, Arakawa, Kazuto, Fitzgerald, Steven P., Edmondson, Philip D., and Roberts, Steve G. High temperature annealing of ion irradiated tungsten. United States: N. p., 2015. Web. doi:10.1016/j.actamat.2015.01.067.
Ferroni, Francesco, Yi, Xiaoou, Arakawa, Kazuto, Fitzgerald, Steven P., Edmondson, Philip D., & Roberts, Steve G. High temperature annealing of ion irradiated tungsten. United States. doi:10.1016/j.actamat.2015.01.067.
Ferroni, Francesco, Yi, Xiaoou, Arakawa, Kazuto, Fitzgerald, Steven P., Edmondson, Philip D., and Roberts, Steve G. Sat . "High temperature annealing of ion irradiated tungsten". United States. doi:10.1016/j.actamat.2015.01.067. https://www.osti.gov/servlets/purl/1265312.
@article{osti_1265312,
title = {High temperature annealing of ion irradiated tungsten},
author = {Ferroni, Francesco and Yi, Xiaoou and Arakawa, Kazuto and Fitzgerald, Steven P. and Edmondson, Philip D. and Roberts, Steve G.},
abstractNote = {In this study, transmission electron microscopy of high temperature annealing of pure tungsten irradiated by self-ions was conducted to elucidate microstructural and defect evolution in temperature ranges relevant to fusion reactor applications (500–1200°C). Bulk isochronal and isothermal annealing of ion irradiated pure tungsten (2 MeV W+ ions, 500°C, 1014 W+/cm2) with temperatures of 800, 950, 1100 and 1400°C, from 0.5 to 8 h, was followed by ex situ characterization of defect size, number density, Burgers vector and nature. Loops with diameters larger than 2–3 nm were considered for detailed analysis, among which all loops had View the MathML source and were predominantly of interstitial nature. In situ annealing experiments from 300 up to 1200°C were also carried out, including dynamic temperature ramp-ups. These confirmed an acceleration of loop loss above 900°C. At different temperatures within this range, dislocations exhibited behaviour such as initial isolated loop hopping followed by large-scale rearrangements into loop chains, coalescence and finally line–loop interactions and widespread absorption by free-surfaces at increasing temperatures. An activation energy for the annealing of dislocation length was obtained, finding Ea=1.34±0.2 eV for the 700–1100°C range.},
doi = {10.1016/j.actamat.2015.01.067},
journal = {Acta Materialia},
number = ,
volume = 90,
place = {United States},
year = {Sat Mar 21 00:00:00 EDT 2015},
month = {Sat Mar 21 00:00:00 EDT 2015}
}

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Cited by: 26works
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