The melting temperature of irradiated oxide fuel

Junji Komatsu, Toshimichi Tachibana, Kenji Konashi

Research output: Contribution to journalArticlepeer-review

22 Citations (Scopus)

Abstract

The melting temperature of oxide fuel is generally considered to decrease with increasing of burnup because of the buildup of fission products. Melting temperatures were measured for UO2 and (U, Pu)O2 fuels. The (U, Pu)O2 specimens were irradiated to a burnup of 110 GWd/t in FBR. The solidus temperatures of (U, Pu)O2 were almost independent of burnup up to 50 GWd/t. The melting temperatures were correlated with Pu content, oxygen-to-metal ratio of the fuel and burnup by ideal solution theory.

Original languageEnglish
Pages (from-to)38-44
Number of pages7
JournalJournal of Nuclear Materials
Volume154
Issue number1
DOIs
Publication statusPublished - 1988 Jun
Externally publishedYes

ASJC Scopus subject areas

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

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