Studies on surface oxide films of stainless steels having simulated post-irradiated grain boundary chemistries

K. S. Raja, Takashi Masuda, Tetsuo Shoji, Yunju Lee

研究成果: Conference contribution

1 被引用数 (Scopus)

抄録

Passive films of specimens having bulk chemistry that simulate the post irradiated grain boundary chemistry of type 304 stainless steel (S.S) were studied in-situ using contact electric resistance (CER) method in a static autoclave containing high temperature pure water. For comparison, conventional stainless steels also were tested. The results show that the passive films of the materials having simulated chemistry were of 'n' type semiconductors as in the case of conventional S.S. High phosphorus containing material showed higher electric resistance of passive film at all the test conditions whereas, high Si containing material showed passive film instability at high temperature, which could be associated with the dissolution of silicates. Moreover, the CER data associated with the instability in the passive film of high Si material could be correlated with the observed higher crack growth rate in PWR primary water environment. There is a possible correlation between the observed electric resistance data of the passive film of type 316 S.S and the published data on SSRT of type 316. In addition, CER measurements were carried out on Ni-Cr alloys with different Cr contents. Ni base alloys with 8-16% Cr content showed 'n' type behavior of passive film. Alloy 690 type material showed 'p' type passive film. Higher electric resistance of passive films of 8% Cr and 16% Cr samples could be correlated with the observed SCC susceptibility during SSRT.

本文言語English
ホスト出版物のタイトルProceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -
編集者S. Bruemmer, P. Ford, G. Was
出版社Minerals, Metals and Materials Society
ページ1125-1134
ページ数10
ISBN(印刷版)0873394755, 9780873394758
DOI
出版ステータスPublished - 1999 1 1
外部発表はい
イベントProceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors - - New Portbeach, CA, United States
継続期間: 1999 8 11999 8 5

出版物シリーズ

名前Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -

Other

OtherProceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -
国/地域United States
CityNew Portbeach, CA
Period99/8/199/8/5

ASJC Scopus subject areas

  • 工学(全般)

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