Microstructure evolution in titanium carbide with different stoichiometry under 3 MeV Au2+ ion irradiation

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-02-01 DOI:10.1016/j.jnucmat.2025.155609

Jinyu Shi , Yiming Lei , Chenxu Wang , Jie Zhang , Jingyang Wang

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Abstract

Titanium carbide (TiC) with the merits of stability and corrosion resistance has been regarded as promising structural material candidate for advanced nuclear reactors. The effects of deviation in carbon stoichiometry and local ordering of carbon vacancies on the irradiation-induced microstructure evolution of TiC_x (x = 0.62–0.98) were targeted. 3 MeV Au²⁺ ion irradiation at room temperature (RT) was conducted over a series of ion fluences ranging from 1 × 10¹⁴ to 2 × 10¹⁶ ions cm^-2, together with grazing incidence X-ray diffraction (GIXRD) and transmission electron microscopy (TEM). No amorphization was traced for titanium carbide ceramics with different stoichiometry irradiated at doses up to ∼70 displacements per atom (dpa). Substoichiometric titanium carbides exhibited excellent lattice expansion resistance compared to near stoichiometric one beyond a dose of ∼30 dpa. In addition, irradiation-induced two ordered phases and twins were observed. Local ordering of C vacancies benefits the accommodation, annihilation of irradiation induced defects, which enhances the tolerance of irradiation-induced amorphization of titanium carbide ceramics. This work provides a comprehensive understanding of microstructure evolution in titanium carbide with different stoichiometry, which facilitates the application of titanium carbide ceramics as advanced reactors cores concepts.

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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.