About this Abstract |
| Meeting |
MS&T24: Materials Science & Technology
|
| Symposium
|
Ceramic Materials for Nuclear Energy Systems
|
| Presentation Title |
Post-irradiation Examination of Irradiated Fuels with Pulsed Neutrons at LANSCE |
| Author(s) |
Sven C. Vogel, Thilo Balke, Charles A. Bouman, Luca Capriotti, Aaron E. Craft, Jason M. Harp, Alex M. Long, Kenneth J. McClellan, Josef Svoboda, Brendt E. Wohlberg, Michael T. Benson |
| On-Site Speaker (Planned) |
Sven C. Vogel |
| Abstract Scope |
Neutrons offer bulk, non-destructive characterization of irradiated materials for which other bulk methods, e.g., X-ray tomography, are not suitable due to the immense gamma background emitted from the samples. In particular, pulsed neutrons provide information from the ability to resolve the neutron energy using their time-of-flight. This enables to utilize neutron absorption resonance to characterize the density of fission and neutron capture products non-destructively. Neutron diffraction provides information on the microstructure (texture, crystallographic phases and their phase fractions). Both of these techniques may ultimately be applied to the bulk of an irradiation capsule prior to destructive post-irradiation examination to identify regions of interest, thus maximizing insight from expensive irradiation campaigns. As a step towards this goal, an Advanced Test Reactor irradiated U-10Zr-1Pd sample was characterized at LANSCE with an NSUF funded rapid turnaround experiment (RTE). |