Evaluation of swelling behaviour of buffer materials containing bentonite for repositories of high-level nuclear waste

Research output: Contribution to conferencePaper

Abstract

Compacted bentonite and compacted sand-bentonite mixture are attracting greater attention as buffer materials for disposal pits in the underground facilities for repositories of high-level nuclear waste. Buffer materials must have swelling characteristics and are expected to fill up the space between the material and surrounding ground by swelling. This role is called as “Self-sealing.” To design the specifications, such as dry density, sand-bentonite mass ratio and size, of buffer material, this study proposed the new evaluation formulas for swelling characteristics of buffer materials containing bentonite. The applicability of the evaluation formula proposed in this study has been confirmed by comparing the predicted results with laboratory test results on the swelling deformation and swelling pressure of compacted bentonites and sand-bentonite mixtures. The evaluation formulas proposed can obtain the maximum swelling pressure and the maximum swelling strain of buffer materials at various dry densities, kinds of bentonite, and bentonite contents. Therefore, the evaluation formulas can be used for selecting a kind of bentonite which is suitable for buffer material, and for designing the sand-bentonite mass ratio and compaction density from the viewpoint of “Self-sealing”.

Original languageEnglish
Publication statusPublished - 2018 Jan 1
Externally publishedYes
EventISRM International Symposium 2000, IS 2000 - Melbourne, Australia
Duration: 2000 Nov 192000 Nov 24

Other

OtherISRM International Symposium 2000, IS 2000
CountryAustralia
CityMelbourne
Period00/11/1900/11/24

Fingerprint

Radioactive Waste
Bentonite
bentonite
radioactive wastes
repository
swelling
radioactive waste
Swelling
Buffers
buffers
evaluation
sands
self sealing
Sand
sand
dry density
sealing
mass ratios
material
disposal

ASJC Scopus subject areas

  • Geochemistry and Petrology
  • Geophysics

Cite this

Komine, H. (2018). Evaluation of swelling behaviour of buffer materials containing bentonite for repositories of high-level nuclear waste. Paper presented at ISRM International Symposium 2000, IS 2000, Melbourne, Australia.

Evaluation of swelling behaviour of buffer materials containing bentonite for repositories of high-level nuclear waste. / Komine, Hideo.

2018. Paper presented at ISRM International Symposium 2000, IS 2000, Melbourne, Australia.

Research output: Contribution to conferencePaper

Komine, H 2018, 'Evaluation of swelling behaviour of buffer materials containing bentonite for repositories of high-level nuclear waste', Paper presented at ISRM International Symposium 2000, IS 2000, Melbourne, Australia, 00/11/19 - 00/11/24.
Komine H. Evaluation of swelling behaviour of buffer materials containing bentonite for repositories of high-level nuclear waste. 2018. Paper presented at ISRM International Symposium 2000, IS 2000, Melbourne, Australia.
Komine, Hideo. / Evaluation of swelling behaviour of buffer materials containing bentonite for repositories of high-level nuclear waste. Paper presented at ISRM International Symposium 2000, IS 2000, Melbourne, Australia.
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