Powder metallurgical fabrication of zirconium matrix cermet nuclear fuels
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Two powder metallurgical fabrication methods for a zirconium-based cermet nuclear dispersion fuel with oxide microspheres have been demonstrated. A multi-pass, cold-drawing process is shown to have excellent capability to control the final matrix density, though it requires several high-temperature anneals during fabrication to relieve strain hardening and increase matrix-particle bonding. Severe oxide particle damage was observed in the cold-drawn fuel pin and was likely a result of high matrix deformation resistance at room temperature. A single-pass, hot-extrusion process has been demonstrated and was shown to be capable of providing a dense matrix phase with less particle damage. Both processes were shown to be effective fabrication methods for a zirconium-based cermet, and the process variables may be controlled to create the desired fuel properties. 2009 Springer Science+Business Media, LLC.
Journal of Materials Science
author list (cited authors)
Totemeier, A. R., & McDeavitt, S. M.
complete list of authors
Totemeier, Aaron R||McDeavitt, Sean M