About this Abstract |
Meeting |
2023 TMS Annual Meeting & Exhibition
|
Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components III
|
Presentation Title |
Hydride Reorientation Behavior in ZIRLO Using Ring Compression Tests |
Author(s) |
Soyoung Kang, Arthur Motta, Maxim Gussev, Michael Billone |
On-Site Speaker (Planned) |
Soyoung Kang |
Abstract Scope |
The hydrogen picked up during corrosion of nuclear fuel cladding can precipitate as zirconium hydrides when the terminal solid solubility is exceeded. When cooling is performed under sufficient stress, zirconium hydrides can macroscopically re-orient along the cladding radial direction. This hydride reorientation severely degrades cladding ductility. The purpose of this study is to observe the effect of alloy microstructure (i.e., grain shape and grain size) on hydride reorientation especially comparing ZIRLO and Low Tin ZIRLO. These materials have similar crystallographic texture and chemistry, but different microstructures due to the different heat treatments used. Ring compression tests (RCT) were used to apply stress to make reoriented hydrides. Finite element modeling (FEM) was performed to analyze the stress state in the ring samples. From FEM and microstructural characterization, it was possible to determine the threshold stress of hydride reorientation for both materials and the effects of microstructure on hydride reorientation are shown. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Other, |