About this Abstract |
Meeting |
MS&T24: Materials Science & Technology
|
Symposium
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Ceramic Materials for Nuclear Energy Systems
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Presentation Title |
Compositionally Complex Carbide Ceramics: A Perspective on Irradiation Damage |
Author(s) |
Bai Cui, Lanh Trinh, Fei Wang, Kaustubh Bawane, Khalid Hatter, Zilong Hua, Linu Malakkal, Lingfeng He, Luke Wadle, Yongfeng Lu |
On-Site Speaker (Planned) |
Bai Cui |
Abstract Scope |
Extensive experimental and computational studies have demonstrated outstanding physical and chemical properties of the novel materials of compositionally complex carbides (CCC), enabling their promising applications in advanced fission and fusion energy systems. This presentation provides a comprehensive overview of radiation damage behavior reported in the literature to understand the fundamental mechanisms related to the impact of multi-principal metal components on phase stability, irradiation-induced defect clusters, irradiation hardening, and thermal conductivity of compositionally complex carbides. Several future research directions are recommended to critically evaluate the feasibility of designing and developing new ceramic materials for extreme environments using the transformative “multi-principal component” concept. Compared to the existing materials for nuclear applications including stainless steels, nickel alloys, ZrC, SiC, and potentially high-entropy alloys, as well as certain other compositionally complex ceramic families, CCC appear to be more resistant to amorphization, growth of irradiation defect clusters, and void swelling. |