Allen, C.C., Lane, D.L., Palmer, R.A., Jonston, R.G. (1984), “Experimental studies of packing material stability”, In Scientific Basis for Nuclear Waste Management, pp. 105-112.
Alonso, J., Cormenzana, J.L. (2005), NF-PRO deliverable (D-No.: 5.1.1), Part 1. Phenomenological description, Reference Concept (Spent Fuel - Carbon Steel Canister - Bentonite - Granite).
Bollingerfehr, W., Filbert, W., Wehrmann, J. (2008), “A new approach for direct disposal of spent fuel into deep vertical boreholes in a salt repository-8232”, Proceedings of the WM2008 Conference, February 24-28, 2008, Pheonix, Arizona, pp. 1-9.
Börgesson, L., Karnland, O., Johannesson, L.E., Gunnarsson, D. (2006), Current status of SKB's research, development and demonstration programme on buffer, backfill and seals, SKB IC-122.
Bradley, D.J., Coles, D.C., Hodge, P.N., McVay, G.L., Westerman, R.E. (1983), Nuclear waste package material testing report: basaltic and tuffaceous environments, ONWI-4452, Office of Nuclear Waste Isolation.10.2172/60288
Cho, W.J. (2019), Bentonite_barrier material for radioactive waste disposal, KAERI/GP-535/2019, KAERI, pp. 34.
Cho, W.J., Lee, J.O., Choi, H.J. (2014), Thermal conductivity of domestic compacted bentonite and bentonite-sand mixture, KAERI/TR-5561/2014, KAERI.
Choi, H.J., Choi, J. (2008), “Double-layered buffer to enhance the thermal performance in a high-level radioactive waste disposal system”, Nuclear Engineering and Design, Vol. 238, No. 10, pp. 2815-2820.10.1016/j.nucengdes.2008.04.017
Choi, Y.C., Cho, W.J., Lee, J.O., Kim, G.Y. (2019), “Experimental data analysis during initial In-DEBS operation”, Journal of Nuclear Fuel Cycle and Waste Technology, Vol. 17, No. S, pp. 81-95.10.7733/jnfcwt.2019.17.S.81
Couture, R.A. (1985), “Steam rapidly reduces the swelling capacity of bentonite”, Nature, Vol. 318, No. 6041, pp. 50-52.10.1038/318050a0
Cuadros, J., Linares, J. (1996), “Experimental kinetic study of the smectite-to-illite transformation”, Geochimica et Cosmochimica Acta, Vol. 60, No. 3, pp. 439-453.10.1016/0016-7037(95)00407-6
Eberl, D., Hower, J. (1976), “Kinetics of illite formation”, Geological Society of America Bulletin, Vol. 87, No. 9, pp. 1326-1330.10.1130/0016-7606(1976)87<1326:KOIF>2.0.CO;2
Graf, R., Filbert, W. (2006), “Disposal of spent fuel from German nuclear power plants-Paper Work or Technology”, Presentation at the Topseal Conference, 17-20, September, Olkiluoto, Finland, pp. 28-34.
Grauer, R. (1986), Bentonite as a backfill material in the high-level waste repository: chemical aspects, Nagra Technical Report 86-12E.
Grim, R.E. (1968), Clay Mineralogy, McGraw-Hill Book Company, New York, pp. 313-329.
Hicks, T.W., Crawford, M.B. (2002), Co-disposal of HLW and spent fuel with ILW and LLW viability study: Hydro-Thermo-Mechanical effects, Galson Sciences Report 9902-1.
Hicks, T.W., White, M.J., Hooker, P.J. (2009), Role of bentontie in determination of thermal limits on geological disposal facility design, 0883-1 Ver.2, Galson Sciences LTD.10.1115/ICEM2009-16241
Hökmark, H. (2005), Temperature buffer test - Comparison of modelling results/experimental findings: causes of differences, Advances in Understanding Engineered Clay Barriers, Balkema Publishers, Leiden.
Huang, W.L., Longo, J.M., Pevear, D.R. (1993), “An experimentally derived kinetic model for smectite-to-illite conversion and its use as a geothermometer”, Clays and Clay Minerals, Vol. 41, No. 2, pp. 162-177.10.1346/CCMN.1993.0410205
Ikonen, K. (2005), Thermal analysis of repository for spent EPR-type fuel, Posiva Oy Report POSIVA 2005-06.
JNC (2000), H12: Project to establish the scientific and technical basis for HLW disposal in Japan, Second Progress Report on Research and Development for the Geological Disposal of HLW in Japan, Supporting Report 2: Repository Design and Engineering Technology, JNC TN1410 2000-003.
Johnson, L., Gaus, I., Wieczorek, K., Mayor, J.C., Sellin, P., Villar, M.V., Samper, J., Cuevas, J., Gens, A., Velasco, M., Turrero, M.J., Montenegro, L., Martin, P.L., Armand, G. (2014), Integration of the short-term evolution of the engineered barrier system (EBS) with the long-term safety perspective, NAB 14-079, NAGRA, Wettingen.
Johnson, L.H., Tait, J.C., Shoesmith, D.W., Crossthwaite, J.L., Gray, M.N. (1994), The disposal of Canada's nuclear fuel waste: engineered barriers alternatives, Atomic Energy of Canada Limited Report, AECL-10718, COG-93-08.
KAERI (2006), High-level radwaste disposal technology development - HLW disposal system development, KAERI/RR-2765.
KAERI (2011), Geological disposal of pyroprocessed waste from PWR spent nuclear fuel in Korea, KAERI/TR-4525/2011.
Karnland, O. (2005), Laboratory experiments concerning compacted bentonite contacted to high pH solutions, Clay Technology AB, Final Report, European Commission Report EUR 21921.
Karnland, O., Olsson, S., Nilsson, U. (2006), Mineralogy and sealing properties of various bentonites and smectite-rich clay minerals, SKB Technical Report TR-06-30.
Kawamura, H., McKinley, I.G., Neall, F.B. (2008), “Practical and safe implementation of disposal with prefabricated EBS modules”, International Technical Conference on Practical Aspects of Deep Radioactive Waste Disposal Session 2, No. 8.
Kim, J.S., Kwon, S.K., Sanchez, M., Cho, G.C. (2011), “Geological storage of high level nuclear waste”, KSCE Journal of Civil Engineering, Vol. 15, No. 4, pp. 721-737.10.1007/s12205-011-0012-8
Kober, F., Vomboris, S. (2017), “GTS HotBENT Project”, ISCO, Handeck, June 13, NAGRA.
Lee, C., Yoon, S., Cho, W.J., Jo, Y., Lee, S., Jeon, S., Kim, G.Y. (2019), “Study on thermal, hydraulic and mechancial properties of KURT granite and Geongju bentonite”, Journal of Nuclear Fuel Cycle and Waste Technology, Vol. 17, No. S, pp. 65-80.10.7733/jnfcwt.2019.17.S.65
Lee, J.O., Cho, W.J., Hahn, P.S. (2004), “Hydraulic-Thermal-Mechanical properties and radionuclide release-retarding capacity of Kyungju bentonite”, Journal of Nuclear Fuel Cycle and Waste Technology, Vol. 2, No. 2, pp. 87-96.
Leupin, O.X., Birgersson, M., Karnland, O., Korkeakoski, P., Sellin, P., Mäder, U., Wersin, P. (2014), Montmorillonite stability under near-field conditions, NAGRA TR-14-12.
Martin, P.L., Barcala, J.M. (2005), Effects of over-heating on the performance of the engineering clayed barriers of the mock-up test, Advances in Understanding Engineered Clay Barriers, Taylor & Francis Group, London.
Masuda, S., Umeki, H., McKinley I., Kawamura, H. (2004), “Management with CARE”, Nuclear Engineering International, Vol. 49, No. 604, pp. 26-29.
McKinley, I.G., Neall, F.B., Smith, P.A., West, J.M., Kawamura, H. (2004), “Evolution of the cavern-extended storage (CES) concept for flexible management of HLW”, Scientific Basis for Nuclear Management XXVII (MRS2003 Conference), pp. 931-936.10.1557/PROC-807-931
McKinley, I.G., Apted, M. (2007), CARE: Optimiation of deep geological disposal options in Korea, Presentation in KAERI.10.1016/S1569-4860(06)09003-6
Meunier, A., Velde, B. (2004), Iillite, Springer, pp. 286.10.1007/978-3-662-07850-1
MOTIE (2016), A basic national plan for HLW management, Ministry of Trade, Industry and Energy.
Müller-Vonmoos, M., Kahr, G., Bucher, F., Madsen, F.T. (1990), “Investigation of Kinnekulle K-bentonite aimed at assessing the long term stability of bentonites under repository conditions”, Engineering Geology, Vol. 28, No. 3-4, pp. 269-280.10.1016/0013-7952(90)90012-P
NUMO (2004), Development of repository concepts for volunteer siting environments, NUMO Technical Report No. NUMO-TR-04-03.
ONDRAF/NIRAS (2001), Technical overview of the SAFIR 2 report, Safety Assessment and Feasibility Interim Report 2, ONDRAF/NIRAS report NIROND 2001-05 E.
Pedersen, K., Motamedi, M., Karnland, O., Sandén, T. (2000), “Mixing and sulphate-reducing activity of bacteria in swelling, compacted bentonite clay under high-level radioactive waste repository conditions”, Journal of Applied Microbiolology, Vol. 89, No. 6, pp. 1038-1047.10.1046/j.1365-2672.2000.01212.x11123477
PNC (1992), Research and devleopment on geological disposal of high-level radioactive waste - First progress report (H3), Power Reactor and Nuclear Fuel Development Corporation (PNC) - PNC TN1410 93-059.
POSIVA (2008), Quality assurance of the bentonite material, POSIVA Working Report 2008-33 Finland.
Pusch, R. (1983), Stability of deep-sited smectite minerals in crystalline rock-chemical aspects, SKBF/KBS TR 83-16, Sweden.
Pusch, R. (1999), Is montmorillonite-rich clay of MX-80 type the ideal buffer for isolation of HLW?, SKB Technical Report TR-99-33.
Pusch, R. (2008), Geological storage of radioactive waste, Springer-Verlag, Berlin.10.1007/978-3-540-77333-7
Pusch, R., Bluemling, P., Johnson, L.H. (2003), “Performance of strongly compressed MX-80 pellets under repository-like conditions”, Applied Clay Science, Vol. 23, No. 1-4, pp. 239-244.10.1016/S0169-1317(03)00108-X
Radhakrishna, H.S. (1984), Thermal properties of clay-based buffer materials for a nuclear fuel waste disposal vault, AECL-7805, Atomic Energy of Canada Limited.
Rothfuchs, T. (1986), Investigation of thermally induced water release from polyhalitic rock salt under in situ conditions:Temperature test 5 at the Asse salt mine, European Commission Report EUR10392 DE, In German with English Abstract.
Sena, C., Salas, J., Arcos, D. (2010), Aspects of geochemical evolution of the SKB near field in the frame of SR-Site, SKB Technical Report, TR-10-59, SKB, Sweden.
SKB (2003), Thermal dimensioning of the deep repository, Technical Report TR-03-09, Sweden.
SKB (2004). RD&D-programme 2004, Programme for research, development and demonstration of methods for the management and disposal of nuclear waste, TR-04-21, Swedish Nuclear Fuel and Waste Manangement Co., Stockholm.
SKB (2006), Buffer and backfill process report for the safety assessment SR-Can, SKB Technical Report TR-06-18.
SKB (2016), RD&D Programme 2016, Programme for research, development and demonstration of methods for the management and disposal of nuclear waste, TR-16-15, Swedish Nuclear Fuel and Waste Manangement Co., Stockholm.
SNL (2007), Total system performance assessment data input package for requirements analysis for DOE SNF/HLW and Naval SNF waste package physical attributes basis for performance assessment, DOC.20070921.0009, Sandia National Laboratories.
Tohata, I., Kuntiwattanakul, P., Oishi, K., Takeuchi, N. (1998), “Effect of elevated temperature on mechanical behaviour of clays”, Tsuchi To Kiso, Vol. 46, No. 10, pp. 27-30 (in Japanese).10.1346/CCMN.1998.0460104
Tsang, C.F., Bernier, F., Davies, C. (2005), “Geohydromechanical processes in the excavation damaged zone in crystalline rock, rock salt, and indurated and plastic clays-in the context of radioactive waste disposal”, International Journal of Rock Mechanics and Mining Sciences, Vol. 42, No. 1, pp. 109-125.10.1016/j.ijrmms.2004.08.003
Villar, M.V., Lloret, A. (2007), “Dismantling of the first section of the FEBEX in situ test: THM laboratory tests on the bentonite blocks retrieved”, Physics and Chemistry of the Earth, Parts A/B/C, Vol. 32, No. 8-14, pp. 716-729.10.1016/j.pce.2006.03.009
Vomvoris, S., Birkholzer, J., Zheng, L., Gaus, I., Blechschmidt, I. (2015), “THMC behavior of clay-based barriers under high temperature - from laboratory to URL scale”, Proceedings of the International High-Level Radioactive Waste Management Conference, Charleston, NC, USA, pp. 678-687.
Wersin, P., Johnson, L.H., McKinley, I.G. (2007), “Performance of the bentonite barrier at temperatures beyond 100°C: A critical review”, Physics and Chemistry of the Earth, Parts A/B/C, Vol. 32, No. 8-14, pp. 780-788.10.1016/j.pce.2006.02.051
Wickham, S.M. (2008), Evolution of the near-field of the ONDRAF/NIRAS repository concept for category C wastes, NIROND-TR Report 2007-07E.
Yau, Y.C., Peacor, D.R., Essene, E.J., Lee, J.H., Kuo, L.C., Cosca, M.A. (1987), “Hydrothermal treatment of smectite, illite, and basalt to 460°C: Comparison of Natural with hydrothermally formed clay minerals”, Clays and Clay Minerals, Vol. 35, No. 4, pp. 241-250.10.1346/CCMN.1987.0350401
- Publisher :Korean Tunneling and Underground Space Association
- Publisher(Ko) :한국터널지하공간학회
- Journal Title :Journal of Korean Tunnelling and Underground Space Association
- Journal Title(Ko) :한국터널지하공간학회 논문집
- Volume : 21
- No :5
- Pages :587-609
- Received Date :2019. 05. 28
- Revised Date :2019. 07. 29
- Accepted Date : 2019. 08. 02