About this Abstract |
Meeting |
2023 TMS Annual Meeting & Exhibition
|
Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components III
|
Presentation Title |
Cladding Coating Integrity Quantified by Ring Pull and Local Strain Analysis |
Author(s) |
Peter Beck, Mathew Hayne, Emily Proehl, Samuel A Briggs, Julie D Tucker, Tarik A Saleh, Benjamin Eftink |
On-Site Speaker (Planned) |
Peter Beck |
Abstract Scope |
Evaluating the impact of hoop direction strains on thin-walled tubes is a critical step before employing potential nuclear reactor fuel cladding concepts. This is particularly important for Accident Tolerant Fuel (ATF) claddings with coatings to ensure adherence of the coating during service. In this work, we will present developments extending the strain analysis of ring pull testing, a simple to perform hoop direction mechanical test that uses small segments of cladding tube. A novel, LANL developed, Python-based analysis package is combined with digital image correlation and used for calculating the strain field on the rings to correlate local material response to strain. This is applied to measuring the mechanical integrity of Cr coatings on Zircaloy-4 tube. This coating integrity and response to strain will be related to the microstructure at the coating/clad interface. |
Proceedings Inclusion? |
Planned: |