Characterization of plasma in the HiPIMS facility for simulation of fusion-oriented W co-deposition in He/H2 and He/D2 environments

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-02-03 DOI:10.1016/j.jnucmat.2025.155675

Maksim M. Kharkov , Gleb S. Lomonosov , Mikhail S. Novikov , Dobrynya V. Kolodko , Alexander V. Tumarkin , Vitaly S. Efimov , Olga V. Ogorodnikova , Andrey V. Kaziev

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引用次数: 0

Abstract

A new facility based on a HiPIMS (high-power impulse magnetron sputtering) discharge plasma with a hot tungsten (W) target for the investigation of co-deposition of W with helium (He) and hydrogen (H₂, D₂) isotopes on W substrate was developed. To find the ion fluxes from He/H₂ and He/D₂ plasma together with W ions from W target incident on installed samples, the ion mass spectrometric study of a HiPIMS plasma was performed. The results reveal a mixed composition of ion fluxes consisting mainly of monoatomic H⁺(D⁺) and He⁺, diatomic H₂⁺(D₂⁺) and HeH⁺, and triatomic H₃⁺ ions. The content of tungsten ions does not exceed 2 % in any of the explored discharge regimes. The contributions of different species to the total flux are strongly affected by the discharge pulsing parameters, especially pulsed power density. For pulsed power densities below 200 W/cm², H₃⁺ ions in the He/H₂ or D₃⁺ in He/D₂ gas mixtures dominate in the ion flux. The opposite situation of monoatomic ion fraction (H⁺ and D⁺) prevailing over molecular ions is observed in the case of the pulse power density above the values: 400 W/cm² for prevailing of H⁺ in He/H₂ gas mixture discharge, and 900 W/cm² for prevailing of D⁺ in He/D₂ gas mixture discharge. The most suitable discharge modes are selected for future simulation of W co-deposition processes with He/H₂ and He/D₂ gas mixtures. Preliminary data on the thickness of co-deposits in various regimes have been obtained. The He retention in W irradiated at the HiPIMS facility in hydrogen plasma with ∼ 10 % He ion seeding was validated by comparison with the experimental data after irradiation of W under the same conditions in a linear plasma device.

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来源期刊

Journal of Nuclear Materials 工程技术-材料科学：综合

CiteScore

5.70

自引率

25.80%

发文量

601

审稿时长

63 days

期刊介绍： The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.