Irradiation effects in tungsten-copper laminate composite

L. M. Garrison; Y. Katoh; L. L. Snead; T. S. Byun; J. Reiser; M. Rieth

doi:10.1016/j.jnucmat.2016.09.020

Irradiation effects in tungsten-copper laminate composite

L. M. Garrison, Y. Katoh, L. L. Snead, T. S. Byun, J. Reiser, M. Rieth

Research output: Contribution to journal › Article › peer-review

34 Scopus citations

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. For elevated temperature tensile tests after irradiation, the composite only had ductile failure at temperatures where the tungsten was delaminating or ductile.

Original language	English
Pages (from-to)	134-146
Number of pages	13
Journal	Journal of Nuclear Materials
Volume	481
DOIs	https://doi.org/10.1016/j.jnucmat.2016.09.020
State	Published - Dec 1 2016

Funding

This research was supported by the U.S. Department of Energy, Office of Science, Fusion Energy Sciences . This manuscript has been authored by UT-Battelle, LLC, under Contract No. DE-AC05-00OR22725 with the U.S. Department of Energy . The authors would like to thank T. Colling, S. Curlin, M. Gussev, D. Lewis, M. McAlister, A. Williams, and S. Zinkle for their assistance with these experiments and manuscript.

Funders	Funder number
U.S. Department of Energy
Office of Science
Fusion Energy Sciences	DE-AC05-00OR22725

Keywords

Fusion material
Laminate composite
Neutron irradiation
Plasma-facing material
Tungsten

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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10.1016/j.jnucmat.2016.09.020

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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. For elevated temperature tensile tests after irradiation, the composite only had ductile failure at temperatures where the tungsten was delaminating or ductile.",

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AU - Garrison, L. M.

AU - Katoh, Y.

AU - Snead, L. L.

AU - Byun, T. S.

AU - Reiser, J.

AU - Rieth, M.

PY - 2016/12/1

Y1 - 2016/12/1

N2 - 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. For elevated temperature tensile tests after irradiation, the composite only had ductile failure at temperatures where the tungsten was delaminating or ductile.

AB - 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. For elevated temperature tensile tests after irradiation, the composite only had ductile failure at temperatures where the tungsten was delaminating or ductile.

KW - Fusion material

KW - Laminate composite

KW - Neutron irradiation

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KW - Tungsten

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ER -

Irradiation effects in tungsten-copper laminate composite

Abstract

Funding

Keywords

UN SDGs

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