| About this Abstract |
| Meeting |
MS&T24: Materials Science & Technology
|
| Symposium
|
Tackling Metallic Structural Materials Challenges for Advanced Nuclear Reactors
|
| Presentation Title |
Understanding Corrosion Behavior of AA6061 Cladding Material Exposed to Nuclear Reactor Cooling Water Environments |
| Author(s) |
Jenifer S. Locke, Koushik Kosanam, Xiaolei Guo, Saba Esmaeely, Gabby Montiel, Jason Schulthess, Jan-Fong Jue, Jeffery J Giglio |
| On-Site Speaker (Planned) |
Jenifer S. Locke |
| Abstract Scope |
AA6061 is hot isostatically pressed (HIP) around nuclear fuel plates when utilized as cladding material in some advanced test reactors (ATRs). While the AA6061 is protected by a boehmite layer several microns in thickness and the cooling water used in ATRs has relatively low conductivity and low chloride concentrations, the ability for corrosion to occur because of hafnium (Hf) induced galvanic corrosion, crevice corrosion from surface crevice-like sites, boehmite breakdown, and/or HIP produced secondary phase microstructures when exposed to cooling water was investigated. Current results examining the corrosion behavior of AA6061 in the T6 temper in simulated cooling water show that galvanic corrosion with Hf is unlikely and crevice corrosion can occur when the boehmite layer has broken down and/or when HIP effected microstructures are directly exposed to crevice solutions. Work is ongoing to understand the impact of HIP processing parameters on the corrosion behavior for HIP specific microstructures. |