2O3、Y2O3 和 ZrO2的抗輻射性具有重要意義。利用 SRIM 程序模擬了不同能量、不同類型的入射離子對不同材料的影響，分析了不同輻照劑量下氧化鋯的輻照損傷。結(jié)果表明，隨著入射離子能量的增加，入射離子在靶材中的分布趨于均勻，入射離子的停止位置和靶材的損傷深度有所增加。入射離子的種類不同，對靶材的損傷程度也大不相同，不利于對比材料的抗輻射能力。在相同的輻照條件下，入射離子的分布隨輻照劑量的增加保持不變，但輻照損傷會不斷累積直至飽和。在6種物質(zhì)中，氧化鋯和碳化鋯的抗輻射性能較好。對氧化鋯增強的鎢合金在700 ℃進行碳離子輻照實驗，發(fā)現(xiàn)氧化鋯具有良好的輻照性能。;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."/>