Dry recovery of ceramic uranium dioxide waste material

I. Schwartz, M. H. Mintz, Z. Hadari

Research output: Contribution to journalArticlepeer-review

5 Scopus citations

Abstract

Three dry recovery routes of ceramic uranium dioxide waste material were studied: (a) calcination of waste material to U3O8 and blending with the original UO2 powder; (b) calcination to U3O8, then reduction to UO2 and blending with the original UO2 powder; (c) grinding the waste material to a fine powder and blending with the original UO2 powder. The first route resulted in an increased open porosity and decreased closed porosity of the sintered UO2 pellets. The second recovery route had almost no effect on the quality of the sintered pellets, while the third route caused an increase in open porosity up to about 15-18 wt% of the added scrap material and increased closed porosity for higher concentrations of the added recovery material. Effects of sieving the recovered scrap powders were also investigated. No effects were observed for the first and second recovery routes, while for the third route more pronounced effects were obtained for coarsely ground powders.

Original languageEnglish
Pages (from-to)54-59
Number of pages6
JournalJournal of Nuclear Materials
Volume82
Issue number1
DOIs
StatePublished - 1 Jan 1979

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Materials Science (all)
  • Nuclear Energy and Engineering

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