About this Abstract |
Meeting |
MS&T22: Materials Science & Technology
|
Symposium
|
High Temperature Oxidation of Metals and Ceramics
|
Presentation Title |
Burst Behavior and Oxidation Resistance of Cr-coated Zircaloy-4 Accident Tolerant Fuel Cladding |
Author(s) |
Mackenzie Ridley, Samuel Bell, Ben Garrison, Tim Graening, Kenneth Kane, Nathan Capps |
On-Site Speaker (Planned) |
Mackenzie Ridley |
Abstract Scope |
Accident tolerant fuel cladding concepts are being researched to enhance the safety and reliability of light water nuclear reactors without disrupting energy efficiencies. Cr-coated zirconium alloys represent a leading cladding concept for industrial application. In this work, unirradiated Cr-coated Zircaloy-4 was exposed to simulated loss of coolant accident conditions, where claddings were internally pressurized and rapidly heated to examine cladding burst behavior. The effect of Cr coatings on burst behavior, rupture geometry, and oxidation resistance will be discussed. This work was supported by the United States Department of Energy, Office of Nuclear Energy, Advanced Fuels Campaign. |