不同化学计量碳化钛的离子辐照损伤行为研究

doi:10.15541/jim20250228

摘要/Abstract

摘要： 第四代核反应堆服役环境苛刻，高温和强辐照对结构材料提出了更高的要求，亟需开发新型抗辐照材料。碳化钛陶瓷(TiC_x)因其高熔点、优异的力学性能、良好的耐腐蚀性而成为先进核反应堆中极具潜力的结构材料。本研究采用3MeV Au²⁺对不同化学计量碳化钛薄膜进行辐照实验，系统研究了TiC_x缺陷结构、表面形貌和力学性能在不同辐照通量下的变化规律。结果表明：随辐照通量的增加，近化学计量TiC_x晶格无序化程度加剧，而亚化学计量TiC_x辐照后的结构稳定性优异。亚化学计量TiC_x在辐照后表面粗糙度无明显变化且未产生辐照裂纹。此外，TiC_x在辐照后硬度和模量均呈现增加趋势，其中亚化学计量TiC_x的抗辐照硬化能力优于近化学计量样品。这主要是由于亚化学计量TiC_x的本征碳空位有效抑制了辐照缺陷的累积，从而维持了良好的稳定性。本研究结果对于理解化学计量与过渡金属碳氮化合物辐照损伤之间的关系及设计新型抗强辐照陶瓷新材料提供了重要的参考依据。

关键词: 碳化钛薄膜离子辐照, 结构分析, 表面形貌, 力学性能

Abstract:

Gen IV nuclear reactors operate in extreme service environments characterized by high temperature and intense irradiation, imposing stringent demands on structural materials and thus necessitating the development of novel irradiation resistant materials. Titanium carbide (TiC_x) ceramic is considered as promising structural materials for advanced nuclear reactors, attributed to its high melting point, excellent mechanical properties, and excellent corrosion resistance. In this study, TiC_x films with different stoichiometry were irradiated with 3 MeV Au²⁺, aiming to systematically investigate irradiation-induced changes in structural characteristics, surface morphology, and mechanical properties under different irradiation fluences. The results revealed that the structural disorder of TiC_x intensified with irradiation fluence increasing, while the substoichiometric TiC_x maintained superior structural stability after irradiation. The surface roughness of sub-stoichiometric TiC_x showed no significant variation after irradiation, with no irradiation-induced crack formed. Additionally, both hardness and elastic modulus of TiC_x exhibited an increasing trend after irradiation, with substoichiometric TiC_x demonstrated enhanced resistance to irradiation hardening compared to near-stoichiometric counterparts. The native carbon vacancies in substoichiometric TiC_x effectively suppresses the accumulation of irradiation-induced defects, thereby preserving excellent stability. This study provides critical insights into the relationship between stoichiometry and irradiation damage in TiC_x, while also offering valuable guidance for designing new classes of irradiation-resistant ceramic materials.

Key words: titanium carbide films, ion irradiation, structural analysis, surface morphology, mechanical properties

中图分类号:

TB43

石金瑜, 雷一明, 王晨旭, 张洁, 王京阳. 不同化学计量碳化钛的离子辐照损伤行为研究[J]. 无机材料学报, DOI: 10.15541/jim20250228.

SHI Jinyu, LEI Yiming, WANG Chenxu, ZHANG Jie, WANG Jingyang. Ion Irradiation Damage Behavior in Titanium Carbide with Different Stoichiometry[J]. Journal of Inorganic Materials, DOI: 10.15541/jim20250228.

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