NSUF 18-1589: Irradiation Damage in (Hf0.2Zr0.2Ta0.2Nb0.2Ti0.2)C High-Entropy Ceramics
The objective of this project is examine the irradiation damage behavior in the novel high-entropy ceramics (HEC) as the potential candidate materials for the extreme environments in next-generation nuclear energy systems. A novel high-entropy carbide ceramic, (Hf0.2Zr0.2Ta0.2Nb0.2Ti0.2)C, with a single-phase rock salt structure, has been recently developed in the PI’s lab. To our knowledge, there has been no report on the irradiation damage behavior in HEC. The hypothesis is that HECs such as (Hf0.2Zr0.2Ta0.2Nb0.2Ti0.2)C have higher irradiation tolerance than binary carbide ceramics (such as ZrC, HfC), because the significant chemical disorder and lattice distortion can slow energy dissipation and suppress formation of irradiation defects. This proposed work will investigate (i) helium irradiation induced bubbles and defect clusters in (Hf0.2Zr0.2Ta0.2Nb0.2Ti0.2)C at 800 °C to ~5 dpa, and (ii) heavy ion irradiation induced defect clusters at room temperature and 800 °C to ~20 dpa. The scientific outcome will be the fundamental knowledge of irradiation resistance of (Hf0.2Zr0.2Ta0.2Nb0.2Ti0.2)C in terms of microstructure stability with insights into the nature and type of irradiation defects in this novel material. This will help predict the in-service degradation of HEC in advanced nuclear reactor environments such as VHTR and GFR, in which ceramic materials are being actively pursued as fuel cladding materials
Additional Info
| Field | Value |
|---|---|
| Abstract | The objective of this project is examine the irradiation damage behavior in the novel high-entropy ceramics (HEC) as the potential candidate materials for the extreme environments in next-generation nuclear energy systems. A novel high-entropy carbide ceramic, (Hf0.2Zr0.2Ta0.2Nb0.2Ti0.2)C, with a single-phase rock salt structure, has been recently developed in the PI’s lab. To our knowledge, there has been no report on the irradiation damage behavior in HEC. The hypothesis is that HECs such as (Hf0.2Zr0.2Ta0.2Nb0.2Ti0.2)C have higher irradiation tolerance than binary carbide ceramics (such as ZrC, HfC), because the significant chemical disorder and lattice distortion can slow energy dissipation and suppress formation of irradiation defects. This proposed work will investigate (i) helium irradiation induced bubbles and defect clusters in (Hf0.2Zr0.2Ta0.2Nb0.2Ti0.2)C at 800 °C to ~5 dpa, and (ii) heavy ion irradiation induced defect clusters at room temperature and 800 °C to ~20 dpa. The scientific outcome will be the fundamental knowledge of irradiation resistance of (Hf0.2Zr0.2Ta0.2Nb0.2Ti0.2)C in terms of microstructure stability with insights into the nature and type of irradiation defects in this novel material. This will help predict the in-service degradation of HEC in advanced nuclear reactor environments such as VHTR and GFR, in which ceramic materials are being actively pursued as fuel cladding materials |
| Award Announced Date | 2018-09-17T12:08:21.88 |
| Awarded Institution | Center for Advanced Energy Studies |
| Facility | Microscopy and Characterization Suite |
| Facility Tech Lead | Alina Zackrone, Lin Shao, Yaqiao Wu |
| Irradiation Facility | None |
| PI | Bai Cui |
| PI Email | [email protected] |
| Project Type | RTE |
| RTE Number | 1589 |