About this Abstract |
| Meeting |
MS&T25: Materials Science & Technology
|
| Symposium
|
Manufacturing and Processing of Advanced Ceramic Materials
|
| Presentation Title |
Pulsed Neutron Characterization of Additively Manufactured Annular UO2 Fuels |
| Author(s) |
Cheng Sun, Sven Vogel, Patrick Moo, Donald Brown, Bjorn Clausen |
| On-Site Speaker (Planned) |
Cheng Sun |
| Abstract Scope |
In recent years, significant development of advanced manufacturing technologies allows novel designs to overcome limitations imposed by conventional nuclear fuel fabrication methods and fuel geometries. Here, we report digital light processing of annular UO2 fuel pellets and their characterization using neutron diffraction and neutron computed tomography (CT). From neutron diffraction, we found significant amount of uranium carbide, likely resulting from binder used during the printing process reacting during sintering. From the cold neutron, we identified regions where uranium carbide has the highest concentration, thus guiding destructive examination of the pellets. The results indicate that neutron diffraction and tomography are ideal tools to characterize additive manufactured ceramic materials, allowing for optimization of digital light processing for advanced nuclear fuel development. |