Behavior of fission products zirconium and barium in fastreactor fuel irradiated to high burnup

Isamu Sato, Hirotaka Furuya, Tatsumi Arima, Kazuya Idemitsu, Kazuya Yamamoto

Research output: Contribution to journalArticle

24 Citations (Scopus)

Abstract

Barium and Zr generated in nuclear fuels can precipitate as multi-component oxide with some other fission products. In addition, the solubility of Ba in the fuel depends on the oxygenpotential and the temperature and Zr can easily dissolve into the fuel matrix. Therefore, the behavior of the Ba-Zr oxide inclusions during irradiation is rather complex. In this work, the composition of multi-component oxides and the distributions of Ba and Zr as a function of relative radius were evaluated with X-ray microanalysis. As results, the oxide inclusions containing bothBa and Zr and containing only Ba were observed in the fuel irradiated to the burnup of 13.3 and 10.6 at%, respectively. These results were discussed in terms of the solubility of Ba and Zr in the fuel and in terms of the rO2–UO2 phase diagram, together with the radial distributions of Ba and Zr in fuel matrix.

Original languageEnglish
Pages (from-to)775-780
Number of pages6
Journaljournal of nuclear science and technology
Volume36
Issue number9
DOIs
Publication statusPublished - Sep 1999

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

Fingerprint Dive into the research topics of 'Behavior of fission products zirconium and barium in fastreactor fuel irradiated to high burnup'. Together they form a unique fingerprint.

  • Cite this