Quantitative assessment of Ni+ and He+ ion irradiation damage in a tungsten heavy alloy under the simulated nuclear fusion environment

A 90W-7Ni-3Fe (wt.%) tungsten heavy alloy has been sequentially Ni<sup>+</sup> and He<sup>+</sup> ion irradiated at 700 °C to simulate the high temperature irradiation environment of a fusion reactor interior. W/Ni-Fe-W dual-phase alloys have been proposed to serve as plasma facing materials and require detailed investigation of their behavior under fusion relevant conditions to assess their overall applicability. To evaluate material performance under five years of simulated fusion reactor service, microstructural characterization of the nanoscale defect distribution has been performed on both constituent phases, revealing peak swelling in the W phase of approximately 0.03%. The γ-phase (Ni-Fe-W) is found to swell approximately 0.68% under the same irradiation conditions, indicating significant cavity formation and growth. Additionally, a novel multi-projection imaging approach has been applied to determine the extent of damage segregation along the dual-phase W-to-γ interface and exposes that these interfaces act as sink sites for the accumulation of cavities. Interphase boundaries are noted to possess an 11.8% areal coverage of defects along the boundary plane, primarily on the γ-phase side of the boundary. The accumulation of cavities at these interphase boundaries is anticipated to adversely affect overall material toughness, and this work reveals a pressing need for mechanical property testing of irradiated W-Ni-Fe dual-phase alloys.

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Publication Details

Journal
Scientific Reports
Published
2025-02-27
DOI
https://doi.org/10.1038/s41598-025-89532-w
Citations
2
Primary Topic
Fusion materials and technologies
Type
article
Field-Weighted Citation Impact
1.04

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article

Quantitative assessment of Ni+ and He+ ion irradiation damage in a tungsten heavy alloy under the simulated nuclear fusion environment

Weilin Jiang, Matthew J. Olszta, Yucheng Fu, Bethany E. Matthews et al.
2 citations
Scientific Reports
Fusion materials and technologies
1.04
article

Quantitative assessment of Ni+ and He+ ion irradiation damage in a tungsten heavy alloy under the simulated nuclear fusion environment

Weilin Jiang, Matthew J. Olszta, Yucheng Fu, Bethany E. Matthews, Wahyu Setyawan, Danny J. Edwards, James V. Haag
article en
2 citations

Abstract

A 90W-7Ni-3Fe (wt.%) tungsten heavy alloy has been sequentially Ni<sup>+</sup> and He<sup>+</sup> ion irradiated at 700 °C to simulate the high temperature irradiation environment of a fusion reactor interior. W/Ni-Fe-W dual-phase alloys have been proposed to serve as plasma facing materials and require detailed investigation of their behavior under fusion relevant conditions to assess their overall applicability. To evaluate material performance under five years of simulated fusion reactor service, microstructural characterization of the nanoscale defect distribution has been performed on both constituent phases, revealing peak swelling in the W phase of approximately 0.03%. The γ-phase (Ni-Fe-W) is found to swell approximately 0.68% under the same irradiation conditions, indicating significant cavity formation and growth. Additionally, a novel multi-projection imaging approach has been applied to determine the extent of damage segregation along the dual-phase W-to-γ interface and exposes that these interfaces act as sink sites for the accumulation of cavities. Interphase boundaries are noted to possess an 11.8% areal coverage of defects along the boundary plane, primarily on the γ-phase side of the boundary. The accumulation of cavities at these interphase boundaries is anticipated to adversely affect overall material toughness, and this work reveals a pressing need for mechanical property testing of irradiated W-Ni-Fe dual-phase alloys.

Scientific ReportsVol. 15(1)
Pacific Northwest National Laboratory (US)
U.S. Department of Energy, Battelle, Office of Science, Fusion Energy Sciences, Pacific Northwest National Laboratory
Openalex Percentile: Top 27%
Fusion materials and technologies
1.04
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