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

H. Watanabe, T. Muroga, N. Yoshida

Research output: Contribution to journalConference articlepeer-review

6 Citations (Scopus)

Abstract

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.

Original languageEnglish
Pages (from-to)381-384
Number of pages4
JournalJournal of Nuclear Materials
Volume271-272
DOIs
Publication statusPublished - May 1999
EventProceedings of the 1997 8th International Conference on Fusion Reactor Materials (ICFRM-8), Part C - Sendai, Jpn
Duration: Oct 26 1997Oct 31 1997

All Science Journal Classification (ASJC) codes

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

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