NSUF 21-4357: Investigation of Degradation Mechanisms of Cr coated Zirconium alloy cladding in Reactive Initiate Accidents (RIA)
Researchers will investigate the thermal, mechanical, and irradiation response of chromium-coated zirconium alloy claddings under RIA conditions, in comparison to uncoated Zr-alloy cladding. The outcome of the project will be used for anticipated licensing applications to the U.S. Nuclear Regulatory Commission (NRC), thereby accelerating use of coated accident tolerant fuel concepts in U.S. commercial power reactors.
Additional Info
| Field | Value |
|---|---|
| Abstract | Researchers will investigate the thermal, mechanical, and irradiation response of chromium-coated zirconium alloy claddings under RIA conditions, in comparison to uncoated Zr-alloy cladding. The outcome of the project will be used for anticipated licensing applications to the U.S. Nuclear Regulatory Commission (NRC), thereby accelerating use of coated accident tolerant fuel concepts in U.S. commercial power reactors. |
| Award Announced Date | 2021-11-02T12:38:14.68 |
| Awarded Institution | Idaho National Laboratory |
| Facility | Advanced Test Reactor |
| Facility Tech Lead | Alina Zackrone |
| Irradiation Facility | None |
| PI | Hwasung Yeom |
| PI Email | [email protected] |
| Project Type | RTE |
| RTE Number | 4357 |