Reaction of yttria-stabilized zirconia with zirconium, silicon and Zircaloy-4 at high temperature: A compatibility study for cermet fuels

研究成果: Contribution to journalConference article査読

5 被引用数 (Scopus)

抄録

Compatibility studies for cermet (ceramic and metal) fuels have been completed for a temperature range of 1073-1423 K. A reaction between yttria-stabilized zirconia (YSZ), as a simulated fuel, and Zr, as a candidate for a metallic matrix, has been observed at temperatures ≥1273 K, which means the formation of a metallic reaction layer at the interface between YSZ and Zr and the occurrence of metallic phases inside the YSZ. Similar results were observed for the YSZ-Zry4 (cladding) system. On the other hand, the degree of reaction was relatively large for the YSZ-Si (metallic matrix) system, and Si diffused into the YSZ. However, the maximum fuel center-line temperature can be predicted to be less than ≈1273 K for cermet fuels. Therefore, compatibility between the ceramic fuel and the metallic matrix should be good under normal reactor operational conditions. Furthermore, since the temperature of the fuel-cladding gap is lower, the cermet fuel and the cladding material are compatible.

本文言語英語
ページ(範囲)24-30
ページ数7
ジャーナルJournal of Nuclear Materials
319
DOI
出版ステータス出版済み - 6 1 2003
イベントProceedings of the 8th Inert Matrix Fuel Workshop - Tokai, 日本
継続期間: 10 16 200210 18 2002

All Science Journal Classification (ASJC) codes

  • 核物理学および高エネルギー物理学
  • 材料科学(全般)
  • 原子力エネルギーおよび原子力工学

フィンガープリント

「Reaction of yttria-stabilized zirconia with zirconium, silicon and Zircaloy-4 at high temperature: A compatibility study for cermet fuels」の研究トピックを掘り下げます。これらがまとまってユニークなフィンガープリントを構成します。

引用スタイル