In situ study on radiation response of tungsten manufactured by laser powder bed fusion

Yinghang Liu; Tanner O. McElroy; Chang Xia; Adil Wazeer; Yexiang Xue; Guang Lin; Tim Graening; Xiao Ying Yu; Wei Ying Chen; Haiyan Wang; Xinghang Zhang

doi:10.1016/j.jnucmat.2026.156526

In situ study on radiation response of tungsten manufactured by laser powder bed fusion

Yinghang Liu
, Tanner O. McElroy
, Chang Xia
, Adil Wazeer
, Yexiang Xue
, Guang Lin
, Tim Graening
, Xiao Ying Yu
, Wei Ying Chen
, Haiyan Wang
, Xinghang Zhang

Advanced Nuclear Materials

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

Abstract

Tungsten (W) produced by laser powder bed fusion (LPBF) was examined by in situ Krypton (Kr) ion irradiation at 400 °C up to 2.52 displacements per atom (dpa) to investigate its radiation response. Dislocation loops with identical Burgers vectors form aligned raft structures, inducing significant grain misorientation accumulation. Defect saturation was observed beyond 0.36 dpa, marked by constant loop density and raft spacing. WO₃ nanoparticles are found in the as-printed matrix and served as efficient defect sinks. Dislocation loops were absorbed at the W/WO₃ interface, facilitating defect annihilation and suppressing defect accumulation. These findings highlight the role of LPBF microstructure and oxide interfaces in mediating radiation-induced defect evolution, offering insights for designing radiation tolerant W-based materials.

Original language	English
Article number	156526
Journal	Journal of Nuclear Materials
Volume	625
DOIs	https://doi.org/10.1016/j.jnucmat.2026.156526
State	Published - Apr 2026

Funding

We would like to acknowledge the financial support from DOE Fusion Energy Sciences (FES) under grant number DE-SC0024583 . Yu and Graening acknowledge support of the DOE FES Fusion Materials program and the DOE FES RENEW project (76203-5017) at the Oak Ridge National Laboratory (ORNL). ORNL is operated by UT-Battelle, LLC un-der Contract No. DE-AC05-00OR22725 for the U.S. Department of Energy. The United States (US) Government retains and the publisher, by accepting the article for publication, acknowledges that the US Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US Government purposes. The DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan ( http://energy.gov/downloads/doe-public-access-plan ). We also thank Peter M. Baldo and Edward A. Ryan at Argonne National Laboratory for their help during in situ radiation experiments. The IVEM facility at Argonne National Laboratory is supported by DOE-Office of Nuclear Energy. Accesses to the Microscopy Centers at Purdue University and the DoE Center for Integrated Nanotechnologies managed by Los Alamos National Laboratory is also acknowledged. This work was supported by the U.S. Department of Energy, Office of Nuclear Energy under DOE Idaho Operations Office Contract DE-AC07-05ID14517 as part of Nuclear Science User Facilities award #24-4971.

Keywords

Defect sink
Dislocation loop rafts
Laser powder bed fusion (LPBF)
Tungsten (W)
in situ irradiation

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10.1016/j.jnucmat.2026.156526

Cite this

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title = "In situ study on radiation response of tungsten manufactured by laser powder bed fusion",

abstract = "Tungsten (W) produced by laser powder bed fusion (LPBF) was examined by in situ Krypton (Kr) ion irradiation at 400 °C up to 2.52 displacements per atom (dpa) to investigate its radiation response. Dislocation loops with identical Burgers vectors form aligned raft structures, inducing significant grain misorientation accumulation. Defect saturation was observed beyond 0.36 dpa, marked by constant loop density and raft spacing. WO3 nanoparticles are found in the as-printed matrix and served as efficient defect sinks. Dislocation loops were absorbed at the W/WO₃ interface, facilitating defect annihilation and suppressing defect accumulation. These findings highlight the role of LPBF microstructure and oxide interfaces in mediating radiation-induced defect evolution, offering insights for designing radiation tolerant W-based materials.",

keywords = "Defect sink, Dislocation loop rafts, Laser powder bed fusion (LPBF), Tungsten (W), in situ irradiation",

author = "Yinghang Liu and McElroy, \{Tanner O.\} and Chang Xia and Adil Wazeer and Yexiang Xue and Guang Lin and Tim Graening and Yu, \{Xiao Ying\} and Chen, \{Wei Ying\} and Haiyan Wang and Xinghang Zhang",

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year = "2026",

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doi = "10.1016/j.jnucmat.2026.156526",

language = "English",

volume = "625",

journal = "Journal of Nuclear Materials",

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T1 - In situ study on radiation response of tungsten manufactured by laser powder bed fusion

AU - Liu, Yinghang

AU - McElroy, Tanner O.

AU - Xia, Chang

AU - Wazeer, Adil

AU - Xue, Yexiang

AU - Lin, Guang

AU - Graening, Tim

AU - Yu, Xiao Ying

AU - Chen, Wei Ying

AU - Wang, Haiyan

AU - Zhang, Xinghang

PY - 2026/4

Y1 - 2026/4

N2 - Tungsten (W) produced by laser powder bed fusion (LPBF) was examined by in situ Krypton (Kr) ion irradiation at 400 °C up to 2.52 displacements per atom (dpa) to investigate its radiation response. Dislocation loops with identical Burgers vectors form aligned raft structures, inducing significant grain misorientation accumulation. Defect saturation was observed beyond 0.36 dpa, marked by constant loop density and raft spacing. WO3 nanoparticles are found in the as-printed matrix and served as efficient defect sinks. Dislocation loops were absorbed at the W/WO₃ interface, facilitating defect annihilation and suppressing defect accumulation. These findings highlight the role of LPBF microstructure and oxide interfaces in mediating radiation-induced defect evolution, offering insights for designing radiation tolerant W-based materials.

AB - Tungsten (W) produced by laser powder bed fusion (LPBF) was examined by in situ Krypton (Kr) ion irradiation at 400 °C up to 2.52 displacements per atom (dpa) to investigate its radiation response. Dislocation loops with identical Burgers vectors form aligned raft structures, inducing significant grain misorientation accumulation. Defect saturation was observed beyond 0.36 dpa, marked by constant loop density and raft spacing. WO3 nanoparticles are found in the as-printed matrix and served as efficient defect sinks. Dislocation loops were absorbed at the W/WO₃ interface, facilitating defect annihilation and suppressing defect accumulation. These findings highlight the role of LPBF microstructure and oxide interfaces in mediating radiation-induced defect evolution, offering insights for designing radiation tolerant W-based materials.

KW - Defect sink

KW - Dislocation loop rafts

KW - Laser powder bed fusion (LPBF)

KW - Tungsten (W)

KW - in situ irradiation

UR - https://www.scopus.com/pages/publications/105030328928

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DO - 10.1016/j.jnucmat.2026.156526

M3 - Article

AN - SCOPUS:105030328928

SN - 0022-3115

VL - 625

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

M1 - 156526

ER -

In situ study on radiation response of tungsten manufactured by laser powder bed fusion

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Keywords

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