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Title: Irradiation effects in tungsten-copper laminate composite

Abstract

Tungsten-copper laminate composite has shown promise as a structural plasma-facing component as compared to tungsten rod or plate. The present study evaluated the tungsten-copper composite after irradiation in the High Flux Isotope Reactor (HFIR) at temperatures of 410–780 °C and fast neutron fluences of 0.02–9.0 × 1025 n/m2, E > 0.1 MeV, 0.0039–1.76 displacements per atom (dpa) in tungsten. Tensile tests were performed on the composites, and the fracture surfaces were analyzed with scanning electron microscopy. Before irradiation, the tungsten layers had brittle cleavage failure, but the overall composite had 15.5% elongation at 22 °C. After only 0.0039 dpa this was reduced to 7.7% elongation, and no ductility was observed after 0.2 dpa at all irradiation temperatures when tensile tested at 22 °C. In conclusion, tor elevated temperature tensile tests after irradiation, the composite only had ductile failure at temperatures where the tungsten was delaminating or ductile.

Authors:
 [1];  [1];  [2];  [3];  [4]; ORCiD logo [4]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
  3. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
  4. Karlsruhe Institute of Technology, Karlsruhe (Germany)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). High Flux Isotope Reactor (HFIR)
Sponsoring Org.:
USDOE Office of Science (SC), Fusion Energy Sciences (FES)
OSTI Identifier:
1326484
Alternate Identifier(s):
OSTI ID: 1396813
Grant/Contract Number:  
AC05-00OR22725
Resource Type:
Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 481; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; plasma-facing material; laminate composite; fusion material; tungsten; neutron irradiation

Citation Formats

Garrison, L. M., Katoh, Yutai, Snead, Lance L., Byun, Thak Sang, Reiser, Jens, and Rieth, Michael. Irradiation effects in tungsten-copper laminate composite. United States: N. p., 2016. Web. doi:10.1016/j.jnucmat.2016.09.020.
Garrison, L. M., Katoh, Yutai, Snead, Lance L., Byun, Thak Sang, Reiser, Jens, & Rieth, Michael. Irradiation effects in tungsten-copper laminate composite. United States. https://doi.org/10.1016/j.jnucmat.2016.09.020
Garrison, L. M., Katoh, Yutai, Snead, Lance L., Byun, Thak Sang, Reiser, Jens, and Rieth, Michael. Mon . "Irradiation effects in tungsten-copper laminate composite". United States. https://doi.org/10.1016/j.jnucmat.2016.09.020. https://www.osti.gov/servlets/purl/1326484.
@article{osti_1326484,
title = {Irradiation effects in tungsten-copper laminate composite},
author = {Garrison, L. M. and Katoh, Yutai and Snead, Lance L. and Byun, Thak Sang and Reiser, Jens and Rieth, Michael},
abstractNote = {Tungsten-copper laminate composite has shown promise as a structural plasma-facing component as compared to tungsten rod or plate. The present study evaluated the tungsten-copper composite after irradiation in the High Flux Isotope Reactor (HFIR) at temperatures of 410–780 °C and fast neutron fluences of 0.02–9.0 × 1025 n/m2, E > 0.1 MeV, 0.0039–1.76 displacements per atom (dpa) in tungsten. Tensile tests were performed on the composites, and the fracture surfaces were analyzed with scanning electron microscopy. Before irradiation, the tungsten layers had brittle cleavage failure, but the overall composite had 15.5% elongation at 22 °C. After only 0.0039 dpa this was reduced to 7.7% elongation, and no ductility was observed after 0.2 dpa at all irradiation temperatures when tensile tested at 22 °C. In conclusion, tor elevated temperature tensile tests after irradiation, the composite only had ductile failure at temperatures where the tungsten was delaminating or ductile.},
doi = {10.1016/j.jnucmat.2016.09.020},
journal = {Journal of Nuclear Materials},
number = C,
volume = 481,
place = {United States},
year = {Mon Sep 19 00:00:00 EDT 2016},
month = {Mon Sep 19 00:00:00 EDT 2016}
}

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Cited by: 21 works
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