Hostname: page-component-848d4c4894-2pzkn Total loading time: 0 Render date: 2024-06-02T01:53:32.889Z Has data issue: false hasContentIssue false
  • English
  • Français

Effects of Chloride, Bromide, and Thiosulfate Ions on the Critical Conditions for Crevice Corrosion of Several Stainless Alloys as a Material for Geological Disposal Packages for Nuclear Waste

Published online by Cambridge University Press:  01 January 1992

Guen Nakayama ,
Hisao Wakamatsu  and
Masatsune Akashi
Guen Nakayama
Affiliation:
Research Institute, Ishikawajima-Harima Heavy Industries Co., Ltd. 3-1-15 Toyosu, Koto-ku, Tokyo 135, Japan
Hisao Wakamatsu
Affiliation:
Nuclear Power Division, Ishikawajima-Harima Heavy Industries Co., Ltd. 3-1-15 Toyosu, Koto-ku, Tokyo 135, Japan
Masatsune Akashi
Affiliation:
Research Institute, Ishikawajima-Harima Heavy Industries Co., Ltd. 3-1-15 Toyosu, Koto-ku, Tokyo 135, Japan
Get access

Abstract

In addition to mild steel, several stainless alloys are being proposed as materials for packages for geological disposal of high-level nuclear waste. When buried deep underground, the greatest detriment to the integrity of packages made of these alloys is localized corrosion, for which critical conditions for initiation of crevice corrosion in chloride environments, with or without other ions, need be precisely known.

Crevice corrosion behavior of Type 304 stainless steel, Type 316 stainless steel, Alloy 825, Ti-Gr.1, and Ti-Gr.12 in solutions containing ions of chloride, bromide (these two for their ordinary presence in natural waters), or thiosulphate (this for the likelihood of microbially influenced corrosion) to varying concentrations have been empirically examined. All of these alloys exhibit much the same concentration dependency of crevice corrosion sensitivity for chloride and bromide ions, while Type 304 stainless steel is particularly sensitive to the thiosulphate ion. The region of insensitivity for chloride ion is wider in the increasing order of Type 304 stainless steel, Type 316 stainless steel, Ti-Gr. 1, and Ti-Gr. 12, with that of Alloy 825 lying somewhere in between.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 294: Symposium V – Scientific Basis for Nuclear Waste Management XVI , 1992 , 323
Copyright
Copyright © Materials Research Society 1993

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

1. Tsujikawa, S. and Hisamatsu, Y.; Boshoku Gijutsu (Corr. Eng. Jpn.) 29, 37 (1980) [in Japanese].Google Scholar
2. Tsujikawa, S.: “Repassivation Potential as Crevice Corrosion Characteristic for Austenite and Ferritic Stainless Steels,” Proc. 3rd Soviet-Japanese Seminar on Corrosion and Protection, Ed. by Kolotyrikin, Ya. M., NAUKA Publishers, p. 119 (1984).Google Scholar
3. Fukuda, T. and Akashi, M.; Corrosion/92, Paper No.92 (1992).Google Scholar
4. Ishikawa, H., Amemiya, K., Yusa, Y. and Sasaki, N.: “Comparison of Fundamental Properties of Japanese Bentonite as Buffer Material for Waste Disposal,” presented to 9th Int. Clay Conf., Strasbourg, France (1989).Google Scholar