Japan Society of Civil Engineers 2020 Annual Meeting

Presentation information

[共通セッション] 放射性廃棄物処分

放射性廃棄物処分(4)

Chair:Yoichi Yamamoto(NUMO)

[CS12-36] Relationship between montmorillonite content and strength of bentonite under the influence of heat

〇Rie Suzuki1, Shin-ichi Kanazawa1, Masaki Yanai1, Ishiyama Koji2 (1.National Institute of Technology, Fukushima College, 2.Nishimatsu construction)

Keywords:Bentonite, Silica sand, Unconfined compression strength, Montmorillonite content

At present, underground geological disposal at depths greater than 300 m is considered a viable disposal option for high-level radioactive waste generated from the reprocessing of spent fuel used in nuclear power plants. However, specification details have yet to be completely determined.
This study aims to understand the mechanical properties of bentonite buffer material by employing uniaxial compression tests while giving temperatures between 30 ℃ to 90℃ to bentonite after applying temperatures history 200℃ to bentonite specimens as 6 months.

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