Corrosion behavior of a powdered simulated nuclear waste glass: A corrosion model including diffusion process

Yaohiro Inagaki, H. Furuya, Kazuya Idemitsu, S. Yonezawa

Research output: Contribution to journalArticle

30 Citations (Scopus)

Abstract

Static corrosion tests were performed with a powdered simulated waste glass in deionized water at 90°C for periods of up to 130 days. It was observed that normalized elemental mass loss (NL) values for soluble elements (Li, B, Na and Mo) were larger than those for Si by a factor of three and continued to increase after saturation of Si. A corrosion model (diffusion-combined model), where a diffusion model is combined with a dissolution/precipitation model (reaction path model), was developed and applied to the analysis of experimental results. In the diffusion-combined model, it is assumed that less-soluble elements dissolve into the solution congruently with the silica glass matrix (glass matrix dissolution). On the other hand, it is assumed that soluble elements diffuse through the glass to the surface and dissolve into the solution, in addition to the glass matrix dissolution. The diffusion-combined model can explain the experimental results well, and it is found that the diffusion coefficient is the most effective parameter determining the corrosion behavior.

Original languageEnglish
Pages (from-to)27-34
Number of pages8
JournalJournal of Nuclear Materials
Volume208
Issue number1-2
DOIs
Publication statusPublished - Jan 1 1994

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Radioactive Waste
radioactive wastes
Radioactive wastes
corrosion
Corrosion
Glass
glass
dissolving
Dissolution
matrices
corrosion tests
Deionized water
silica glass
Fused silica
diffusion coefficient
saturation

All Science Journal Classification (ASJC) codes

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

Cite this

Corrosion behavior of a powdered simulated nuclear waste glass : A corrosion model including diffusion process. / Inagaki, Yaohiro; Furuya, H.; Idemitsu, Kazuya; Yonezawa, S.

In: Journal of Nuclear Materials, Vol. 208, No. 1-2, 01.01.1994, p. 27-34.

Research output: Contribution to journalArticle

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