Fluence dependence of defect evolution in austenitic stainless steels during fission neutron irradiation

H. Watanabe, T. Muroga, N. Yoshida

研究成果: ジャーナルへの寄稿会議記事査読

6 被引用数 (Scopus)

抄録

To understand microstructural evolution during fission neutron irradiation, a pure Fe-Cr-Ni ternary alloy, phosphorus-containing model austenitic stainless steels and SUS316 were irradiated in a Japanese Material Testing Reactor (JMTR) at 493 and 613 K. At 493 K, the density of defect cluster increased with the irradiation dose, but there was no significant change in loop density and loop size among all the materials. At 613 K, on the other hand, interstitial type dislocation loops and phosphides were formed in pure ternary and phosphorus-containing alloys, respectively, by an early stage of irradiation. These results suggest that the defect cluster formation at 493 and 613 K is mainly controlled by the cascade damage and long-range migration of free point defects, respectively.

本文言語英語
ページ(範囲)381-384
ページ数4
ジャーナルJournal of Nuclear Materials
271-272
DOI
出版ステータス出版済み - 5月 1999
イベントProceedings of the 1997 8th International Conference on Fusion Reactor Materials (ICFRM-8), Part C - Sendai, Jpn
継続期間: 10月 26 199710月 31 1997

!!!All Science Journal Classification (ASJC) codes

  • 核物理学および高エネルギー物理学
  • 材料科学一般
  • 原子力エネルギーおよび原子力工学

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