The self-sealing function of the clearances between buffer material and overpack and tunnel wall or disposal pit wall and between backfill material and tunnel wall is expected for bentonite which will be used as buffer material and part of the backfill material. In this study, an analytical theory on the clearance filling performance for both materials was constructed. Volumetric swelling ratio of bentonite (Rvs) and maximum clearance ratio that bentonite can fill clearance (Rsmax) were calculated against dry density for different montmorillonite and silica sand contents of bentonites in distilled water and saline water conditions (Horonobe groundwater and synthetic seawater). Both Rvs and Rsmax values decreased with decreasing montmorillonite content and decreased in saline water conditions. The Rvs values in the Horonobe groundwater (ionic strength IS = 0.207 M) were approximately a half of those in distilled water and those in synthetic seawater (IS = 0.64 M) were approximately a half of those in the Horonobe groundwater. In the case that actual sealing performance is judged, not only clearance filling, but also hydraulic conductivity etc. after the clearance was filled must be considered. In the design of buffer material and backfill material, those parameters must be systematically taken into account.
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ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management
October 3–7, 2010
Tsukuba, Japan
Conference Sponsors:
- Nuclear Engineering Division and Environmental Engineering Division
ISBN:
978-0-7918-5453-2
PROCEEDINGS PAPER
An Analytical Model on the Sealing Performance of Space for the Design of Buffer Material and Backfill Material
Haruo Sato
Haruo Sato
Japan Atomic Energy Agency, Horonobe, Hokkaido, Japan
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Haruo Sato
Japan Atomic Energy Agency, Horonobe, Hokkaido, Japan
Paper No:
ICEM2010-40067, pp. 175-184; 10 pages
Published Online:
April 5, 2011
Citation
Sato, H. "An Analytical Model on the Sealing Performance of Space for the Design of Buffer Material and Backfill Material." Proceedings of the ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management. ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management, Volume 2. Tsukuba, Japan. October 3–7, 2010. pp. 175-184. ASME. https://doi.org/10.1115/ICEM2010-40067
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