Corrosion Behavior of a Powdered Simulated Nuclear Waste Glass in the Presence of Bentonite

Yaohiro Inagaki, Hirotaka Furuya, Kazuya Idemitsu, Shigeaki Yonezawa, Sataro Nishikawa, Jitsuya Takada

研究成果: ジャーナルへの寄稿学術誌査読

3 被引用数 (Scopus)


Static corrosion tests of a powdered simulated waste glass were performed in deionized water with and without bentonite at 90°C for periods of up to 130 days. The glass irradiated with thermal neutron for activating Cs in the glass was used as a glass specimen in order to determine the sorption of Cs on bentonite. In the corrosion tests without bentonite, it was observed that normalized elemental mass loss (NL) values for soluble elements (B, Li, Na and Mo) were larger than those for Si by a factor of three and continued to increase after saturation of Si. In the corrosion tests in the presence of bentonite, it was observed that the glass corrosion was enhanced, and a large amount of Cs was sorbed on bentonite. The experimental results were analyzed by use of some corrosion models. The analysis showed that diffusion of the soluble elements is expected to be a dominant process for the glass corrosion, as well as the dissolution/precipitation reactions. In addition, it is expected that the glass corrosion in the presence of bentonite is largely affected by both ion-exchange equilibrium of the aqueous phase with Na-montmorillonite and precipitation of sepiolite from dissolution of dolomite.

ジャーナルjournal of nuclear science and technology
出版ステータス出版済み - 9月 1994

!!!All Science Journal Classification (ASJC) codes

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


「Corrosion Behavior of a Powdered Simulated Nuclear Waste Glass in the Presence of Bentonite」の研究トピックを掘り下げます。これらがまとまってユニークなフィンガープリントを構成します。