Powder metallurgical fabrication of zirconium matrix cermet nuclear fuels

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...

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Veröffentlicht in:Journal of materials science 2009-10, Vol.44 (20), p.5494-5500
Hauptverfasser: Totemeier, Aaron R., McDeavitt, Sean M.
Format: Artikel
Sprache:eng
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Zusammenfassung: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.
ISSN:0022-2461
1573-4803
DOI:10.1007/s10853-009-3767-2