| About this Abstract |
| Meeting |
2022 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior and Degradation of Advanced Nuclear Fuel and Structural Materials
|
| Presentation Title |
Investigation of Degradation Mechanism of Accident Tolerant Fuel (ATF) Coated Cladding Concepts during Interim Storage and Transportation of Used Nuclear Fuels |
| Author(s) |
Evan J. Willing, Hwasung Yeom, Tyler Dabney, Kumar Sridharan, Andrew Nelson, Tim Graening |
| On-Site Speaker (Planned) |
Evan J. Willing |
| Abstract Scope |
Thin coatings for zirconium-alloy light water reactor (LWR) cladding are being explored as near-term accident tolerant fuel (ATF) concepts. However, it is not clear how these ATF coated claddings will perform in the back end of the fuel cycle. For conventional Zr-alloys, delayed hydride cracking (DHC) is a concern in the used fuel interim storage and transportation stages. It is of interest to see how coating influences hydriding and consequently the DHC behavior of the underlying Zr-alloy. In coated cladding design, the effect of the formation of intermetallic compounds at the interface between the coating and the Zr-alloy on mechanical behavior must also be evaluated. The study investigates these effects using Cr coated cladding concepts that are at the forefront in industry. Mechanical properties have been evaluated using nanoindentation, ring compression tests, and ring tensile tests, coupled with microstructural analysis using scanning electron microscopy. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Mechanical Properties, Nuclear Materials, Surface Modification and Coatings |