About this Abstract |
Meeting |
2023 TMS Annual Meeting & Exhibition
|
Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components III
|
Presentation Title |
Evaluating ATF Cladding Mechanical Behavior |
Author(s) |
Benjamin P. Eftink, Peter Beck, Nan Li, Cheng Liu, Mathew Hayne, Hyosim Kim, Tarik Saleh |
On-Site Speaker (Planned) |
Benjamin P. Eftink |
Abstract Scope |
Nuclear fuel cladding development requires an understanding of how mechanical stresses and strains impact the cladding. There are different mechanical testing methods to extract different properties of claddings and coatings. Some of these methods include ring pull, axial tensile, bulge, and micro-cantilever. When combined they can provide a more complete picture of the claddings expected performance. In this talk, two aspects of cladding evaluation are covered for accident tolerant fuel claddings (FeCrAl and Cr coated Zircaloy), hoop direction mechanical properties and Cr coating mechanical integrity. Results will be discussed in terms of the impact of the Zircaloy/Cr coating interface on adhesion and coating cracking susceptibility in addition to considerations when measuring hoop direction properties in cladding tubes. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Surface Modification and Coatings, Mechanical Properties |