利用SRIM分析辐照对碳化物和氧化物陶瓷的影响

弥散强化在改善合金性能方面发挥着重要作用，而碳化物和氧化物陶瓷作为常用的弥散强化颗粒，其稳定性对于应用于恶劣环境的核反应堆中的合金非常重要，因此研究SiC、TiC、ZrC、Al₂O₃、Y₂O₃ 和 ZrO₂的抗辐射性具有重要意义。利用 SRIM 程序模拟了不同能量、不同类型的入射离子对不同材料的影响，分析了不同辐照剂量下氧化锆的辐照损伤。结果表明，随着入射离子能量的增加，入射离子在靶材中的分布趋于均匀，入射离子的停止位置和靶材的损伤深度有所增加。入射离子的种类不同，对靶材的损伤程度也大不相同，不利于对比材料的抗辐射能力。在相同的辐照条件下，入射离子的分布随辐照剂量的增加保持不变，但辐照损伤会不断累积直至饱和。在6种物质中，氧化锆和碳化锆的抗辐射性能较好。对氧化锆增强的钨合金在700 ℃进行碳离子辐照实验，发现氧化锆具有良好的辐照性能。

Analysis of Irradiation Effects on Carbide Ceramics and Oxide Ceramics by SRIM

Dispersion strengthening plays an important role in improving the properties of alloys. The stability of carbide and oxide ceramics, as commonly used dispersion-reinforced particles, is important for alloys applied in nuclear reactors serving in harsh environments, so it is of great significance to study the radiation resistance of SiC, TiC, ZrC, Al₂O₃, Y₂O₃ and ZrO₂. The effects of different energies and different types of incident ions on different materials were simulated by SRIM program, and the irradiation damage of zirconia at different irradiation doses was analyzed. Results show that with the increase in incident ion energy, the distribution of the incident ions in the target material tends to be uniform and normal, and the stop position of the incident ions and the damage depth of the target material increase. The damage to the target material is different under different types of incident ion, which is not conducive to the radiation resistance comparison of the materials. Under the same irradiation conditions, the distribution of incident ions is consistent regardless of the increase in irradiation dose, but irradiation damage is accumulated until saturation. Among these six substances, zirconium oxide and zirconium carbide have better radiation resistance. The irradiation properties of zirconium oxide were verified by carbon ion irradiation experiments for tungsten alloy reinforced by zirconium oxide at 700 °C.