Temperature effects of ion irradiation on the nanostructural features in ductile-phase-toughened tungsten composites

Jiang, Weilin; Haag, IV, James V.; Kovarik, Libor; Matthews, Bethany E.; Chen, Di; Setyawan, Wahyu

doi:10.1063/5.0261025

Title: Temperature effects of ion irradiation on the nanostructural features in ductile-phase-toughened tungsten composites

Journal Article · Thu May 22 00:00:00 UTC 2025 · Journal of Applied Physics

DOI: https://doi.org/10.1063/5.0261025 · OSTI ID:2568200

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Ductile-phase toughened tungsten (DPT W) composites have emerged as promising candidates for load-bearing components behind the plasma-facing tungsten armor in fusion reactors due to their enhanced thermomechanical properties. This study focuses on a composite consisting of W particles embedded in a ductile NiFeW solution matrix, hot-rolled to a thickness reduction of 87% (87R DPT W). Sequential irradiations with Ni2+ and He+ ions were performed to identical doses and helium concentrations at room temperature (RT) and 1273 K. Irradiation at RT produced no discernible nanostructural features due to the immobility of mono-vacancies, whereas cavity formation was observed at 973 K. At 1273 K, the W phase exhibited larger cavities, reduced cavity number density, and lower volumetric swelling compared to 973 K. Notably, nanosized NiFeW precipitates formed within the W phase at 1273 K, a phenomenon absent at 973 K. A new phase of cubic (NiFe)6W6C was also observed at the interphase boundary. In contrast, the NiFeW matrix showed no nanostructural changes at 1273 K, likely due to cavity dissociation. Separate irradiations at 1273 K indicated that Ni2+ ions induced precipitate formation in the W phase, while He+ ions exclusively caused cavity formation. The microstructure of 87R DPT W irradiated at RT and subsequently annealed at 1273 K closely resembled that of material irradiated directly at 1273 K. Like oxide-dispersion-strengthened steels, the observed nanoparticle-embedded W can inhibit dislocation propagation, potentially delaying the ductile-to-brittle transition temperature. These findings highlight the potential of NiFeW nanoparticle-reinforced W composites as irradiation-resistant materials for fusion reactors.

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Sponsoring Organization:: USDOE

Grant/Contract Number:: AC05-76RL01830

OSTI ID:: 2568200

Journal Information:: Journal of Applied Physics, Journal Name: Journal of Applied Physics Journal Issue: 20 Vol. 137; ISSN 0021-8979

Publisher:: American Institute of PhysicsCopyright Statement

Country of Publication:: United States

Language:: English

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