焦绿石
材料科学
辐照
重离子
离子
复合材料
矿物学
核物理学
化学
相(物质)
物理
有机化学
作者
Liang Xu,Min Niu,Hongjie Wang,Lei Su,Hongfei Gao,Lei Zhuang
标识
DOI:10.1016/j.jeurceramsoc.2022.07.015
摘要
Material with superior damage tolerance, chemical durability, and structure stability is of increasing interest in high-level radioactive waste management and structural components for advanced nuclear systems. In this paper, high-entropy (La 0.2 Ce 0.2 Nd 0.2 Sm 0.2 Gd 0.2 ) 2 Zr 2 O 7 with pyrochlore-type structure was synthesized through conventional solid-state method. The as-synthesized high-entropy oxide maintained crystalline after being irradiated by using Au 3+ with 9.0 MeV energy at the fluence of 4.5 × 10 15 ions·cm -2 , indicating its high tolerance to heavy-ion irradiation. The irradiation-induced order-disorder transition from pyrochlore structure to defective fluorite structure occurred in high-entropy (La 0.2 Ce 0.2 Nd 0.2 Sm 0.2 Gd 0.2 ) 2 Zr 2 O 7 . After irradiation, no irradiation-induced segregation was observed at grain boundary. Moreover, the mechanical properties of high-entropy pyrochlore were improved. The heavy-ion irradiation resistance mechanisms of high-entropy pyrochlore were discussed in detail. Our work identified high-entropy (La 0.2 Ce 0.2 Nd 0.2 Sm 0.2 Gd 0.2 ) 2 Zr 2 O 7 can be a promising candidate for immobilization of high-level radioactive waste as well as advanced nuclear reactor system from the perspective of irradiation resistance.
科研通智能强力驱动
Strongly Powered by AbleSci AI