|About this Abstract
||2022 TMS Annual Meeting & Exhibition
||Mechanical Behavior and Degradation of Advanced Nuclear Fuel and Structural Materials
||Progress on Experimental Investigation of Degradation Mechanisms of ATF Coated Cladding under Transient Conditions
||Hwasung Yeom, Tyler Dabney, David Kamerman, Michelle Bales, Logan Crevelt, Zhen Li, Anthony Evans, Brent Heuser, Kumar Sridharan
|On-Site Speaker (Planned)
Chromium coatings on Zr-alloy cladding are being considered for implementation by nuclear industries to enhance reactor safety during accidents as well as to achieve extended burn-up with improved fuel cycle economics. However, there are still knowledge gaps for robust data sets to support licensing and qualification of the designs, including fuel degradation under design-basis accidents. This research project aims at investigating the thermal, mechanical, and irradiation response of Cr-coated Zr-alloy cladding under prototypical reactivity-initiated accidents (RIA), in comparison to that of uncoated Zr-alloy cladding. This presentation will introduce recent progress of this program including experimental plan at TREAT at INL, fabrication of Cr-coated Zr-alloy tubes using physical vapor deposition and cold spray deposition methods, design of static-water test vehicles, and preliminary test results. The experimental data on response of fueled coated cladding under RIAs will provide validation of results of modeling activities for the ATF fuel designs during reactor transients.
||Nuclear Materials, High-Temperature Materials, Characterization