| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components IV
|
| Presentation Title |
Understanding the thermomechanical response of incumbent and ATF fuel claddings to accident transients |
| Author(s) |
Samuel Bell, Nathan Capps, Caleb Massey, Takaaki Koyanagi, Kory Linton, Peter Doyle, Yong Yan, Jason Harp, Nicholas Brown, Jennifer Espersen, Daniel C. Sweeney, Daniel Schappel, Mackenzie Ridley |
| On-Site Speaker (Planned) |
Samuel Bell |
| Abstract Scope |
The thermomechanical response of fuel cladding during light-water reactor accident transients, such as a loss-of-coolant accident (LOCA), directly impacts performance limits under operational conditions. For example, higher burnup levels, pursued to extend cycle lengths and enhance reactor economics, necessitate addressing concerns related to cladding ballooning and fuel relocation and dispersal. Additionally, understanding the safety margins provided by new accident tolerant fuel claddings is essential for the economic viability of these advanced material systems. Over recent years, Oak Ridge National Laboratory has developed unique burst testing capabilities to evaluate both as-received and irradiated cladding specimens under high heating rate accident transients leveraging in-situ techniques like digital image correlation. This study explores the connections between cladding behavior in semi-integral LOCA testing and conventional mechanical testing, revealed largely by using in-situ strain measurements. The versatility of the test bed for other transient conditions, such as cyclic dry-out, is also highlighted. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Mechanical Properties, High-Temperature Materials |