Journal of Inorganic Materials ›› 2026, Vol. 41 ›› Issue (3): 311-321.DOI: 10.15541/jim20250216

• RESEARCH ARTICLE • Previous Articles     Next Articles

Irradiation Defects in Neutron-irradiated 6H-SiC: Thermodynamic and High-temperature Recovery Kinetics

ZHU Fei1(), HAO Xujie1, ZHANG Quangui1, YAN Xinyue1, LIU Hongfei1, ZHANG Bo2, LI Xin3, LIU Defeng3, TUO Yayong1, ZHANG Shouchao1()   

  1. 1. School of Science, Tianjin Chengjian University, Tianjin 300384, China
    2. School of Materials Science and Engineering, Tianjin Chengjian University, Tianjin 300384, China
    3. Aviation Key Laboratory of Science and Technology on Special Condition Monitoring Sensor Technology, Beijing Changcheng Aeronautic Measurement and Control Technology Research Institute, Beijing 101111, China
  • Received:2025-05-19 Revised:2025-07-01 Published:2025-07-16 Online:2025-07-16
  • Contact: ZHANG Shouchao, professor. E-mail: zhshch@tcu.edu.cn
  • About author:ZHU Fei (1983-), male, engineer. E-mail: zhufei2012@tcu.edu.cn
  • Supported by:
    National Undergraduate Training Program for Innovation and Entrepreneurship(202510792019)

Abstract:

Silicon carbide (SiC) is a promising material for nuclear reactor structures due to its excellent radiation resistance and high-temperature performance. The behavior of irradiation damage and the mechanisms of high-temperature recovery in SiC directly affect its service performance and longevity in nuclear environments. This study investigated effects of neutron irradiation on properties of 6H-SiC, with a particular focus on high-temperature recovery mechanisms of irradiation-induced defects. Specifically, defect evolution and thermodynamic responses in nitrogen-doped (ND≈3.0×1019 cm-3) 6H-SiC subjected to neutron irradiation at about 150 ℃ and a fluence of 2.58×1020 n/cm2 followed by isochronal annealing were examined. Integrated techniques and first-principles calculations were employed to comprehensively analyze its structural and property evolution. The key findings were as follows. (1) Significant lattice swelling was observed during the irradiation, with a swelling rate of 0.416% along the a-axis, 0.430% along the c-axis, and 1.310% in the unit cell volume, while all maintaining integrity of the single-crystalline structure. (2) A 14.7% increase in specific heat capacity was recorded, with 375.4 J/g of stored irradiation energy being released during heating from 100 ℃ to 500 ℃. (3) A four-stage defect recovery kinetic model was proposed based on the recovery of lattice parameters and the evolution of Raman spectra: Stage I (room temperature (RT)-600 ℃), primarily dominated by close-range recombination of carbon Frenkel pairs driven by migration energy (Ea) of 0.14 eV; Stage II (600-850 ℃), recombination of silicon Frenkel pairs and migration of carbon interstitials (Ea=0.26 eV); Stage III (850-1200 ℃), lattice reconstruction (Ea=0.65 eV); Stage IV (1200-1500 ℃), long-range diffusion of carbon vacancies (VC) and dissociation of NCVSi complexes (Ea=1.50 eV). (4) The presence of nitrogen-stabilized NCVSi defect configurations was confirmed by a characteristic emission peak at 826 nm (634 cm-1 Raman shift) when excited with 785 nm light. This study quantitatively reveals the defect recovery pathways and migration energies in neutron-irradiated 6H-SiC, providing a critical foundation for evaluating radiation damage, predicting performance, and optimizing annealing processes in nuclear-grade SiC materials.

Key words: irradiation-induced energy storage, specific heat, Raman spectroscopy, defect luminescence, Arrhenius

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