Analysis of Functional Criteria for Buffer Material in a High-level Radioactive Waste Repository

  • W. J. Cho (Korea Atomic Energy Research Institute) ;
  • Lee, J. O. (Korea Atomic Energy Research Institute) ;
  • K. S. Chun (Korea Atomic Energy Research Institute) ;
  • Park, Hyun-Soo (Korea Atomic Energy Research Institute)
  • Published : 1999.02.01

Abstract

This study is intended to analyze the requirements of a buffer material that is one of the major components of the engineered barriers in a high-level radioactive waste repository. The characteristics of potential materials for the buffer in the repository were analyzed and a candidate material was selected. And, based on the current knowledge and the information from various sources, the requirements of a buffer material were evaluated. Finally its quantitative functional criteria on the generic viewpoint has been recommended to be supplied as a guideline for the development of the reference disposal concept and the related buffer material in Korea. The criteria are composed of seven major items, such as hydraulic conductivity, retardation capacity, swelling potential and swelling pressure, thermal conductivity, longevity, organic matter content, and mechanical properties.

Keywords

References

  1. Atomic Energy of Canada Limited Report, AECL-10715, COG-93-5 The disposal of Canada's nuclear fuel waste: engineering for a disposal facility G.R. Simmons;P. Baumgartner
  2. Engineering Geology v.21 Field compaction of bentonite-based backfilling J. Nilsson
  3. Engineering Geology v.21 A study on the compaction properties of potential clay-sand buffer mixtures for use in nuclear fuel waste disposal D.A. Dixon;M.N. Gray;A.W. Thomas
  4. Atomic Energy of Canada Limited Report, AECL-10718, COG-93-8 The disposal of Canada's nuclear fuel waste: engineering barrier alternatives L.H. Johnson;J.C. Tait;D.W. Shoeesmith;J.L. Crosthwaite;M.N. Gray
  5. 10CFR Part 60 Disposal of Wastes in Geologic Repositories U.S. NRC
  6. Final storage of spent fuel - KBS-3 SKBF/KBS
  7. PNC TN1410 93-059 Research and development on geological disposal of high-level radioactive waste PNC
  8. Atomic Energy of Canada Limited Report, AECL-6834 Fuel waste isolation research for the Canada Nuclear Waste Management Program D.J. Cameron
  9. STRIPA Project Report, TR 87-12 State-of-the-art report on potentially useful materials for sealing nuclear waste repositories W.E. Coon
  10. Commission of the European Communities Report, EUR 9115 EN(2 Volumes) The backfilling and sealing of radioactive waste repositories Mott, Hay;Anderson
  11. Metal Handbook, Ninth edition v.13(Corrosion) Corrosion of titanium and titanium alloys R.W. Schutz;D.E. Thomas
  12. Atlas of Electrochemical Equilibrium in Aqueous Solutions Copper N. de Zoubov;C. Vanleugenhaghe;M. Pourbaix;M. Pourbaix(ed.)
  13. Atomic Energy of Canada Limited Report, AECL-10718, COG-93-8 The disposal of Canada's nuclear fuel waste: engineering barrier alternatives L.H. Johnson;J.C. Tait;D.W. Shoeesmith;J.L. Crosthwaite;M.N. Gray
  14. Clay Mineralogy R.E. Grim
  15. Geotechnique in Resource Development, Proc. of 40th Canadian Geotechnical Conference. Regina The hydraulic conductivity of dense clay soils D.A. Dixon;M.N. Gray;S.C.H. Cheung;B.C. Davidson
  16. Technical Report Series no.319 Sealing of underground repositories for radioactive waste IAEA
  17. Geologic Society of America, Special Paper 189 Contaminant migration in saturated unconsolidated geologic deposits R.W. Gillham;J.A. Cherry
  18. Scientific Basis for Nuclear Waste Management Permeability, swelling, and radionuclide retardation properties of candidate backfill materials J.H.Jr. Westsik;L.A. Bray;F.N. Hodges;E.J. Wheelwright;Tope S. V.(Ed.)
  19. SKB Technical Report 87-29 Alteration of isolating properties of dense smectite clay in repository environment as exemplified by seven pre-quartenary clay R. Pusch;L. Borgesson;M. Erlstrom
  20. Applied Clay Science v.9 Hydraulic properties of montmorillonite-quartz and saponite-quartz mixture M.V. Villar;P.Rivas
  21. Scientific Basis for Nuclear Waste Management XXI Influence of temperature on the hydraulic conductivity in compacted bentonite W.J. Cho;J.O. Lee;K.S. Chun
  22. Transport in Porous Media v.14 Diffusion of $^{14}C$ in dense saturated bentonite under steady-state conditions D.W. Oscarson;H.B. Hume
  23. Soil Science Society of Ameria Journal v.51 no.5 Diffusion of srontium and chloride in compacted clay-based materials M.J.L. Robin;R.W. Gillham;D.W. Oscarson
  24. Scientific XII Diffusion of chloride and uranium in compacted sodium bentonite A. Muurinen;P. Penttila-Hiltunen;K. Unsheimo
  25. SKB Technical Report 91-16 Porosity, sorption and diffusivity data compiled for the SKB 91 Study F. Brandberg;K.Skagius
  26. Radiochimica Acta v.39 Migration of fission products, stronitum, technetium, iodine, and cesium in clay B. Torstenfelt
  27. J. of Nucl, and Sci. and Technol. v.29 Effect of dry density on diffusion of some radionuclides in compacted sodium bentointe H. Sato;T. Ashida;Y. Kohara;M. Yui;N. Sasaki
  28. Scientific Basis for Nuclear Waste Management Ⅸ Diffusion mechanisms of strontiun, cesium, and cobalt in compacted sodium bentonite A. Muurinen;J. Rantanen;P. Penttila-Hiltunen
  29. Scientific Basis for Nuclear Waste Management Ⅹ Diffusion mechanisms of strontium and cesium in compacted sodium bentonite A. Muurinen;P. Penttila-Hiltunen;J. Rantanen
  30. Soil Science Society of America Journal v.55 Diffusion of technetium in dense bentonite: transient state N.G. Sawatsky;D.W. Oscarson
  31. Water, Air, and Soil Pollution v.57;58 Diffusion of technetium in dense bentonite N.G. Sawatsky;D.W. Oscarson
  32. Scientific Basis for Nuclear Waste Management XVI Study on Retardation mechanism of $^3H,^{99}Tc,^{237}Np and ^{241}Am$ H. Sato;T. Ashida;Y. Kohara;M. Yui
  33. Scientific Basis for Nuclear Waste Management Diffusion measurements in compacted bentonite B. Torstenfelt(et al.);Tope S. V.(Ed.)
  34. SKB TR 83-34 Radionuclide diffusion and mobilities in compacted bentonite B. Torstenfelt(et al.)
  35. SKB TR 86-14 Migration of fission products and actinides in compacted bentonite B. Torstenfelt;B. Allard
  36. Soil Science Society of America Journal v.56 Diffusion of iodide in compacted bentonite D.W. Oscarson;H.B. Hume;N.G. Sawatsky;S.C.H. Cheung
  37. Radiochimica Acta v.52;53 Effect of bulk density on diffusion for cesium in compacted sodium bentonite K. Miyahara;T. Ashida;Y. Kohara;Y. Yusa;N. Sasaki
  38. Scientific Basis for Nuclear Waste Management Ⅴ Transport of actinides through a bentonite backfill B. Torstenfelt(et al.)
  39. SKB Technical Report 88-30 Rheological properties of sodium smectite clay L. Borgesson;H. Hokmark;O. Karnland
  40. AECL Technical Report 7825 The influence of sand content on swelling pressures and structure developed in statically compacted Na-bentonite M.N. Gray;S.C.H. Cheung;D.A. Dixon
  41. Engineering Geology v.28 Characterization of a French clay barrier and outline of the experimental programme Ph. Ceneste;M. Raynal;R. Atabek;M. Dardaine;J. Oliver
  42. Project Report NGB 85-09 Nuclear Waste Management in Switzerland: Feasibility Studies and Safety Analyses NAGRA
  43. Scientific Basis for Nuclear Waste Management Ⅴ Development of a backfill for containment of high-level nuclear waste E.N. Hodges;J.H.Jr. Westsik;L.A. Bray
  44. SKB TR 94-29 Heat conductivity of buffer material L. Borgesson;A. Fredrikson;L.-E. Johnnesson
  45. KBS-33 Required physical and mechanical properties of buffer masses R. Pusch
  46. Atomic Energy of Canada Limited Report, AECL-7805 Thermal properties of clay-based buffer materials for a nuclear waste disposal vault H.R. Raadhakrishna
  47. Waste Management 86 Thermal analysis for BWIP waste package advanced conceptual design S.C. Yung;R.T. Toyooka;T.B. McCall
  48. Clay Mineralogy R.E. Grim
  49. Scientific Basis for Nuclear Waste Management Ⅶ Experimental studies of packing material stability C.C. Allen;D.L. Lane;R.A. Palmer;R.C. Johnston
  50. Geochimica et Cosmochimica Acta v.42 The reaction of montmorillonite in mixed-layer clay : the effect of interlayer alkali and alkaline earth cations D Eberl
  51. OECD/NEA international Stripa Project overview Volume Ⅲ:Engineered barriers M.N. Gray
  52. Stripa Project Report, TR-91-26 Final report of the rock sealing porject-sealing properties and longevity of smectite clay grouts R. Pusch;O. Karnland;H. Hokmark;T. Sanden;L. Borgessonet
  53. Scientific Basis for Nuclear Waste Management Ⅵ Experimental investigatin of sodium bentonite stability in Hanfor basalt M.L. Wood
  54. Scientific Basis for Nuclear Waste Management Ⅷ Rapid increase of permeability and porosity of bentonite-sand mixture due to alternation by water vapor R.A. Couture
  55. Nature v.318 Steam rapidly reduces the swelling capacity of bentonite R.A. Couture
  56. SAND83-1293 Observations regarding the stability of bentonite of backfill in a high-level waste (HLW) repository in rock salt J.L. Krumhansl
  57. Microbeam Analysis 1986 Effects of irradiation and dry heating on bentonite : a transmission electron microscopy and X-ray diffraction study C.C. Allen;S.A. Rawson;A.D. Roming(Eds.);W.P. Chambers(Eds.)
  58. Office of Nuclear Waste Isolation Report, ONWI-4452 Nuclear waste package material testing report: Basaltic and Tuffaceous environments D.J. Bradley;D.C. Coles;P.N. Hodge;G.L. McVay;R.E. Westerman
  59. Atomic Energy of Canada Limited Technical Record, TR-139 An evaluation of the microbiological activities and possible consequences in a fuel waste disposal vault: a literature review C.I. Mayfield;J.F. Baker
  60. ACS Symposium Series no.100 Consequence of radiation from sorbed transplutonium elements in clays selected for waste isolation R.G. Haire;G.W. Beall
  61. U.S. DOE, Yacca Mountain Site Characterization Report Mined geologic disposal system, Advanced Conceptual Design Report, Vol Ⅱof Ⅳ TRW Environmental Safety System Inc.
  62. Transuranic Nuclides in the Environment, Proc. of Symposium, IAEA-SM-199'51 Interaction of plutonium with complexing substances in soil and natural waste E.A. Bondietti;S.A. Reynolds;M.H. Shanks
  63. Oak Ridge National Laboratory Report, CONF-790602-64 Chemical factors controlling actinide sorption in the environment G.W. Beall;B. Allard
  64. Fundamentals of soil behavior J.K. Mitchell
  65. AECL-7812 Evaluation of phyllosilicates as a buffer component in the disposal of nuclear fuel waste D.W. Oscarson;S.C.H. Cheung