A Compilation and Evaluation of Thermal and Mechanical Properties of Bentonite-based Buffer Materials for a High- level Waste Repository

  • 발행 : 2002.02.01

초록

The thermal and mechanical properties of compacted bentonite and bentonite-sand mixture were collected from the literatures and compiled. The thermal conductivity of bentonite is found to increase almost linearly with increasing dry density and water content of the bentonite. The specific heat can also be expressed as a function of water ontent, and the coefficient of thermal expansion is almost independent on the dry density. The logarithm of unconfined compressive strength and Young’s modulus of elasticity increase linearly with increasing dry density, and in the case of constant dry density, it can be fitted to a second order polynomial of water content. Also the unconfined compressive strength and Young’s modulus of elasticity of the bentonite-sand mixture decreases with increasing sand content. The Poisson’s ratio remains constant at the dry density higher than 1.6 Mg/m$_3$, and the shear strength increases with increasing dry density.

키워드

참고문헌

  1. G. R. Simmons and P. Baumgartner, 'The disposal of Canada's nuclear fuel waste:engineering for a disposal facility,' Atomic Energy of Canada Limited Report, AECL-10715,COG-93-5 (1994)
  2. SKBF/KBS, 'Final storage of spent fuel -KBS- 3' (1983)
  3. W.J. Cho, J.O. Lee, C.H. Kang, and K.S. Chun, 'Physicochemical, mineralogical and mechanical properties of domestic bentonite and bentonite-sand mixture as a buffer material in the high-level waste repository,' KAERI/TR-1388/99. Korea Atomic Energy Research Institute (in Korean) (1999)
  4. L. Borgesson, A. Fredrinkson, and L.-E. Johannesson, 'Heat conductivity of buffer materials,' SKB Technical Report 94-29 (1994)
  5. H. S. Radhakrishna, 'Thermal properties of clay-based buffer materials for a nuclear fuel waste disposal vault,' AECL-7805 (1984)
  6. J. G. Hartley and W. J. Black, 'Transient simultaneous heat and mass transfer in moist, unsaturated soils,' J. of Heat Transfer, Transaction of the ASME, 103, 376 (1981)
  7. JNC, 'H12 Project to establish technical basis for HLW disposal in Japan,' Supporting Report 2, Japan Nuclear Cycle Development Institute, Japan (1999)
  8. M. Kumata, S. Muraoka, K. Shimooka, M. Okamoto, and K. Araki, 'JAERI-M 87-164,In situ buffer material test (I)- Compacted bentonite,' JAERI-M 87-164, Japan Atomic Energy Research Institute(in Japanese) (1987)
  9. M. Kumata, A. Nakagoshi, K, Shimooka, S. Muraoka, and H. Nakamura, 'In situ buffer material test (II)- A preliminary test on a bentonite/sand mixture,' JAERI-M 87-171, Japan Atomic Energy Research Institute (in Japanese) (1987)
  10. S. Knutsson, 'On the thermal conductivity and thermal diffusivity of highly compacted bentonite,' SKB Technical Report 83-72 (1983)
  11. L. Borgesson, H. Honkmark, and O. Karnland, 'Rheological properties of sodium smectite clay,' SKB Technical Report 88-30 (1988)
  12. A. Beziat, M. Dardaine, and V. Gabis, 'Effect of compaction pressure and water content on the thermal conductivity of some natural clays,' Clay and Clay Minerals, 36 462-466 (1988) https://doi.org/10.1346/CCMN.1988.0360512
  13. H. Suzuki, M. Shibata, J. Yamagata, I. Hirose, and K. Terakado, 'Physical and mechanical properties of bentonite (I), PNC TN8410 92-057 (in Japanese) (1992)
  14. K.S. Chun, W.J. Cho, J.O. Lee, S.S. Kim, and M.J. Kang, 'High-level waste disposal technology development- Development of engineered barrier,' 'KAERI/RR-1897/98. Final Repory, MOST (in Korean) (1998)
  15. E. Mongaro et al., 'Characterization of clay(bentonite)/crushed granite mixtures to build barrier against the migration of radionuclides: diffusion studies and physical properties,' EUR 13666 EN, Commission of the European Communities (1990)
  16. H. Susuki, M. Shibata, J. Yamagata, I. Hirose and K. Terakado, 'Physical and mechanical properties of bentonite (I), PNC TN8410 92-057, Power Reactor and Nuclear Fuel Development Corporation (in Japanese) (1992)
  17. K. Takaji and H. Suzuki, 'Static mechanical properties of buffer material,' Japan Nuclear Cycle Development Institute, JNC-TN8400 99-041, Japan Nuclear Fuel Cycle Devolopment Institute (in Japanese) (1999)
  18. T. Fujita, A. Saotome and K. Hara, 'Mechanical properties of buffer material,' PNC TN8410 92-170, Power Reactor and Nuclear Fuel Development Corporation (in Japanese) (1992)
  19. M. Maeda, K. Tanai, M. Ito, M. Mihara, and M. Tanaka, 'Mechanical properties of the Ca-exchanged and Ca bentonite', PNC TN8410 98-021, Power Reactor and Nuclear Fuel Development Corporation (in Japanese) (1998)
  20. K. Takaji and W. Taniguchi, 'Dynamic mechanical properties of buffer material,' Japan Nuclear Cycle Development Institute, JNC Technical Report, JNC-TN8400 99-042 (in Japanese) (1999)
  21. M. Maeda, M. Ito, M. Mihara, and M. Tanaka, Consolidated undrained triaxial test of the Ca-exchanged bentonite,' PNC TN8410 97-314, Power Reactor and Nuclear Fuel development Corporation (in Japanese) (1997)
  22. E. Mingaro et al., 'Characterization of clay(bentonite)/crushed granite mixtures to build barrier against the migration of radionuclides: diffusion studies and physical properties,' EUR 13666 EN, Commission of the European Communities
  23. L. Borgesson and R. Pusch, 'Rheological properties of calcium smectite,' SKB Technical Report 87-31 (1987)
  24. T. W. Lambe, R. V. Whitman, Soil Mechanics, John Wiely and Sons, New York, (1969)
  25. T. Namikawa and T. Kanno, 'Consolidation properties of buffer materials,' Power Reactor and Nuclear Fuel Development Corporation, PNC TN8410, 97-051 (in Japanese) (1997)
  26. W. J. Cho, J. O. Lee and C. H. Kang, 'A compilation and evaluation of thermal and mechanical properties of compacted bentonite for the performance assessment of engineered barriers in the high-level waste repository, Korea Atomic Energy Research Institute, KAERI/TR-1826/2001 (in Korean) (2001)