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Title: Microstructural evolution of pure tungsten neutron irradiated with a mixed energy spectrum

Abstract

Here, microstructures of single-crystal bulk tungsten (W) and polycrystalline W foil with a strong grain texture were investigated using transmission electron microscopy following neutron irradiation at ~90–800 °C to 0.03–4.6 displacements per atom (dpa) in the High Flux Isotope Reactor with a mixed energy spectrum. The dominant irradiation defects were dislocation loops and small clusters at ~90 °C. Additional voids were formed in W irradiated at above 460 °C. Voids and precipitates involving transmutation rhenium and osmium were the dominant defects at more than ~1 dpa. We found a new phenomenon of microstructural evolution in irradiated polycrystalline W: Re- and Os-rich precipitation along grain boundaries. Comparison of results between this study and previous studies using different irradiation facilities revealed that the microstructural evolution of pure W is highly dependent on the neutron energy spectrum in addition to the irradiation temperature and dose.

Authors:
 [1];  [1];  [2];  [1];  [1];  [3];  [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Tohoku Univ., Sendai (Japan)
  3. Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
Publication Date:
Research Org.:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). High Flux Isotope Reactor (HFIR)
Sponsoring Org.:
USDOE Office of Science (SC)
OSTI Identifier:
1357970
Alternate Identifier(s):
OSTI ID: 1396918
Grant/Contract Number:  
AC05-00OR22725
Resource Type:
Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 490; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE

Citation Formats

Koyanagi, Takaaki, Kumar, N. A. P. Kiran, Hwang, Taehyun, Garrison, Lauren M., Hu, Xunxiang, Snead, Lance L., and Katoh, Yutai. Microstructural evolution of pure tungsten neutron irradiated with a mixed energy spectrum. United States: N. p., 2017. Web. doi:10.1016/j.jnucmat.2017.04.010.
Koyanagi, Takaaki, Kumar, N. A. P. Kiran, Hwang, Taehyun, Garrison, Lauren M., Hu, Xunxiang, Snead, Lance L., & Katoh, Yutai. Microstructural evolution of pure tungsten neutron irradiated with a mixed energy spectrum. United States. https://doi.org/10.1016/j.jnucmat.2017.04.010
Koyanagi, Takaaki, Kumar, N. A. P. Kiran, Hwang, Taehyun, Garrison, Lauren M., Hu, Xunxiang, Snead, Lance L., and Katoh, Yutai. Thu . "Microstructural evolution of pure tungsten neutron irradiated with a mixed energy spectrum". United States. https://doi.org/10.1016/j.jnucmat.2017.04.010. https://www.osti.gov/servlets/purl/1357970.
@article{osti_1357970,
title = {Microstructural evolution of pure tungsten neutron irradiated with a mixed energy spectrum},
author = {Koyanagi, Takaaki and Kumar, N. A. P. Kiran and Hwang, Taehyun and Garrison, Lauren M. and Hu, Xunxiang and Snead, Lance L. and Katoh, Yutai},
abstractNote = {Here, microstructures of single-crystal bulk tungsten (W) and polycrystalline W foil with a strong grain texture were investigated using transmission electron microscopy following neutron irradiation at ~90–800 °C to 0.03–4.6 displacements per atom (dpa) in the High Flux Isotope Reactor with a mixed energy spectrum. The dominant irradiation defects were dislocation loops and small clusters at ~90 °C. Additional voids were formed in W irradiated at above 460 °C. Voids and precipitates involving transmutation rhenium and osmium were the dominant defects at more than ~1 dpa. We found a new phenomenon of microstructural evolution in irradiated polycrystalline W: Re- and Os-rich precipitation along grain boundaries. Comparison of results between this study and previous studies using different irradiation facilities revealed that the microstructural evolution of pure W is highly dependent on the neutron energy spectrum in addition to the irradiation temperature and dose.},
doi = {10.1016/j.jnucmat.2017.04.010},
journal = {Journal of Nuclear Materials},
number = C,
volume = 490,
place = {United States},
year = {Thu Apr 13 00:00:00 EDT 2017},
month = {Thu Apr 13 00:00:00 EDT 2017}
}

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Works referencing / citing this record:

Neutron-induced damage simulations: Beyond defect production cross-section, displacement per atom and iron-based metrics
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Selective laser melting of high-performance pure tungsten: parameter design, densification behavior and mechanical properties
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PHENIX U.S.-Japan Collaboration Investigation of Thermal and Mechanical Properties of Thermal Neutron–Shielded Irradiated Tungsten
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Pre-Irradiation Comparison of W-Based Alloys for the PHENIX Campaign: Microstructure, Composition, and Mechanical Properties
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Stress-induced hydrogen self-trapping in tungsten
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Selective laser melting of high-performance pure tungsten: parameter design, densification behavior and mechanical properties
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