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심지층처분장 공학적방벽 성능 실증: 현장실험적 접근법 검토
Validation of Performance of Engineered Barriers in a Geological Repository: Review of In-Situ Experimental Approach 원문보기

Journal of nuclear fuel cycle and waste technology = 방사성폐기물학회지, v.16 no.2, 2018년, pp.137 - 164  

조원진 (한국원자력연구원) ,  김건영 (한국원자력연구원)

초록
AI-Helper 아이콘AI-Helper

심지층처분장 공학적방벽의 성능 보장은 장기처분안전성 측면에서 뿐만 아니라 심지층처분장의 효율적인 설계를 위해서도 매우 중요하다. 따라서 지하실험시설에서 수행되는 현장실험들을 통해 심지층처분장 조건 하에서의 공학적방벽 성능을 입증할 필요가 있다. 이 논문에서는 심지층처분장 공학적방벽의 성능을 실증하기 위해, 지난 수십 년 동안 전 세계에서 수행되어온 주요 현장실험의 현황과 그 결과에 대해 검토하였다. 먼저 심지층처분장의 폐쇄 후 성능을 모사하는 공학적방벽시스템의 열-수리-역학적 복합거동을 규명하기 위한 현장실험들이 분석되었다. 아울러 실제 심지층처분장의 환경에서 완충재의 성능을 조사하기 위한 현장실험들이 검토되었다. 완충재-콘크리트 상호반응, 완충재, 뒷채움재 및 플러그의 설치, 그리고 근계암반 특성과 처분용기 재질의 부식 현상을 규명하기 위한 현장실험들의 기술현황도 분석되었다.

Abstract ▼ AI-Helper 아이콘AI-Helper

The guarantee of the performance of the engineered barriers in a geological repository is very important for the long-term safety of disposal as well as the efficient design of the repository. Therefore, the performance of the engineered barriers under repository condition should be demonstrated by ...

주제어

#현장실험   #공학적방벽   #심지층처분장   #실증   #입증  

참고문헌 (113)

  1. H.J. Choi, J.Y Lee, D.K. Cho, S.K. Kim, S.S. Kim, K.Y. Kim, J.T. Chung, M.S. Lee, J.W. Choi, and J.O. Lee. Korean Reference HLW Disposal System, Korea Atomic Energy Research Institute Report, KAERI/TR-3563/2008 (2008). 

  2. National Cooperative for the Disposal of Radioactive Waste, "Grimsel Test Site Phase VI", International Steering Committee Meeting, June 10-11, 2008, Swiss National Cooperative for Radioactive Waste Management. 

  3. S. Vomvoris, I. Blechschmidt, T. Vietor, and H. Mueller, "NAGRA's Activities at the Grimsel Test Site and the Mont Terri Project: Update and Outlook", High Level Radioactive Waste Management 2015, Charleston (2015). 

  4. National Cooperative for the Disposal of Radioactive Waste, "The Mont Terri Rock Laboratory", NAGRA Bulletin, 34, 24-35 (2002). 

  5. Swedish Nuclear Fuel and Waste Management Company Aspo Hard Rock Laboratory- A Unique Place for Experiments and Research (2016). 

  6. Department of Energy, Yucca Mountain Science and Engineering Report, U. S. Department of Energy Report, DOE/RW-0539-1 (2002). 

  7. Department of Energy, Department of Energy FY 2019 Congressional Budget Request, U. S. Department of Energy Report, DOE/CF-0141 (2018). 

  8. POSIVA. ONKALO URL Homepage, Accessed Jan. 2018, Available from: http://www.posiva.fi/englanti/; ONKALO Situation. 

  9. F. Bernier, X.L. Li, and W. Bastiaens, "Twenty-five Years' Geotechnical Observation and Testing in the Tertiary Boom Clay Formation", Geotechnique, 57, 229-237 (2007). 

    상세보기 crossref

  10. G.Y. Kim, D.S. Bae, J.Y. Lee, and J.H. Park. Establishment of Infrastructure in KURT for In-situ Demonstration, Korea Atomic Energy Research Institute Report, KAERI/RR-3886/2014 (2015). 

  11. Y.W. Tsang, J. Apps, J.T. Birkholzer, B. Freifeld, M.Q. Hu, J. Peterson, E. Sonnenthal, and N. Spycher. Yucca Mountain Single Heater Test Final Report, Yucca Mountain Site Characterization Project, Lawrence Berkeley National Laboratory Report, LBNL-42537 (1999). 

  12. R.E. Finley, S.C. Blair, W.J. Boyle, J.J. Danneels, R.N. Datta, N.Z. Elkins, J.T. George, E.F. Homuth, M.Y. Lee, W.L. Mark, T. Peters, M. Riggins, Y. Tsang, R.A. Wagner, D.J. Weaver, and R.M. Yasek. The Yucca Mountain Project Drift Scale Test, Sandia National Laboratory Report, SAND2000-2362C (2000). 

  13. TRW, Drift Scale Test Design and Forecast Results, TRW Environmental Safety Systems Report, BAB000000-01717-4600-00007 Rev. 00 (1997). 

  14. TRW, Characterization of the Drift Scale Test Block, TRW Environmental Safety Systems Report, RADD00000-01717-5705-00001 Rev. 00 (1997). 

  15. Itasca Consulting Group, FLAC-Fast Lagrangian Analysis of Continua, Version 4.0 (2000). 

  16. K. Pruess, C. Oldenburg, and G. Moridis. TOUGH2 User's Guide, Version 2.0, Lawrence Berkeley National Laboratory Report, LBNL-43134 (1999). 

  17. S. Olivella, A. Gens, J. Carrera, and E. Alonso, "Numerical Formulation for a Simulator 'CODE_BRIGHT' for the Coupled Analysis of Saline Media", Eng. Comput., 13, 87-112 (1996). 

    상세보기 crossref

  18. French Atomic Energy Commission, CASTEM, An Objective Oriented Finite Element Method Framework (2000). 

  19. P.L. Martin and J.M. Barcala, "Large Scale Buffer Material Test: Mock-up Experiment at CIEMAT", Eng. Geol., 81, 298-316 (2005). 

    상세보기 crossref

  20. Empresa Nacional de Residuos Radiactivos S.A., Full-scale Engineered Barriers Experiment, Updated Final Report 1994-2004, ENRESA Technical Publication, 05-0/2006 (2006). 

  21. A.M. Fernandez, N. Jockwer, and P.L. Martin. Evolution of the Chemical Parameters in the FEBEX Insitu Experiment, EC NF-PRO Project Report, D2.2.10 (2007). 

  22. A. Gens, M. Sanchez, L.N. Guimaraes, E.E. Alonso, A. Lloret, S. Olivella, M.V. Villar, and F. Huertas, "A Full-scale In situ Heating Test for High-level Nuclear Waste Disposal: Observation, Analysis and Interpretation", Geotechnique, 59, 377-399 (2009). 

    상세보기 crossref

  23. A.M. Fernandez, A. Muurinen, E. Montarges-Pelletier, N. Jockwer, and P. Rivas, "Geochemical Processes in the FEBEX Bentonite after a Heating and Hydration In-situ Test in the Grimsel URL", Clays in Natural & Engineered Barriers for Radioactive Waste Confinement, 4th Int. Meeting, Nantes (2010). 

  24. F. Kober, I. Gaus, S. Birkholzer, and S. Vomvoris, "18 Years of Heating a Full Scale EBS at $100^{\circ}C$ (FEBEX, Grimsel Test Site) and Possible Applications at Higher Temperatures ("hotFEBEX" at > $150^{\circ}C$ )", Clays in Natural and Engineered Barriers for Radioactive Waste Confinement, 6th International Conference, Brussels (2015). 

  25. E.E. Alonso, J. Alcoverro, F. Coste, L. Malinsky, V. Merrien-Soukatchoff, I. Kadiri, T. Nowak, H. Shao, T.S. Nguyen, A.P. Selvadurai, G. Armand, S.R. Sobolik, M. Itamura, C.M. Stone, S.W. Webb, A. Rejeb, M. Tijani, Z. Maouche, A. Kobayashi, H. Kurikami, A. Ito, Y. Sugita, M. Chijimatsu, L. Borgesson, J. Hernelind, J. Rutqvist, C.-F. Tsang, and P. Jussila, "The FEBEX Benchmark Test: Case Definition and Comparison of Modelling Approaches", Rock Mech. Min. Sci., 42, 611-638 (2005). 

    상세보기 crossref

  26. DECOVALEX-2019, Accessed Jan. 2018, Available from: http://decovalex.org, 2018. 1. 

  27. G.W. Lanyon and I. Gaus. Main Outcomes and Review of the FEBEX In Situ Test (GTS) and Mock-up after 15 years of Operation, National Cooperative for the Disposal of Radioactive Waste Technical Report, 15-04 (2016). 

  28. C. Andersson, I. Barcena, N. Bono, L. Boergesson, P. Cleall, T. Forsmark, D. Gunnarsson, L.E. Johannesson, A. Ledesma, L. Liedtke, A. Luukkonen, K. Pedersen, I. Puigdomenech, R. Pusch, I. Rhen, T. Rothfuchs, T. Sanden, J.L. Sineriz, Y. Sugita1, C. Svemar, and H. Thomas, Full-scale Testing of the KBS-3V Concept for the Geological Disposal of High-level Radioactive Waste, Prototype Repository, EUR Final Report, EUR 21924 (2005). 

  29. Swedish Nuclear Fuel and Waste Management Company, Aspo Hard Rock Laboratory Annual Report 2013, SKB Technical Report, TR-14-17 (2014). 

  30. Swedish Nuclear Fuel and Waste Management Company, Aspo Hard Rock Laboratory Annual Report 2014, SKB Technical Report, TR-15-10 (2015). 

  31. L-E. Johannesson, Prototype Repository, Measurements of Water Content and Density of the Excavated Buffer Material form Deposition Hole 5 and 6 and the Backfill in the Outer Section of the Prototype Repository, Swedish Nuclear Fuel and Waste Management Company Progress Report, P-13-14 (2014). 

  32. S. Olsson, V. Jensen, L-E. Johannesson, E. Hansen, O. Karnland, S. Kumpulainen, D. Svensson, S. Hansen, and J. Linden, Prototype Repository, Hydro-mechanical, Chemical and Mineralogical Characterization of the Buffer and Backfill Material from the Outer Section of the Prototype Repository, Swedish Nuclear Fuel and Waste Management Company Technical Report, TR-13-21 (2013). 

  33. J. Arlinger, A. Bengtsson, J. Edlund, L. Eriksson, J. Johansson, S. Lydmark, L. Rabe, and K. Pedersen, Prototype Repository, Microbes in the Retrieved Outer Section, Swedish Nuclear Fuel and Waste Management Company Progress Report, P-13-16 (2013). 

  34. U. Nilsson, Prototype Repository, Validation of Retrieved Sensors from the Prototype Experiment at Aspo Hard Rock Laboratory, Swedish Nuclear Fuel and Waste Management Company Progress Report, P-13-31 (2014). 

  35. C. Svemar, L-E. Johannesson, P. Grahm, D. Svensson, O. Kristensson, M. Lonnqvist, and U. Nilsson, Prototype Repository, Opening and Retrieval of Outer Section of Prototype Repository at Aspo Hard Rock Laboratory, Summary Report, Swedish Nuclear Fuel and Waste Management Company Technical Report, TR-13-22 (2016). 

  36. R. Pusch, Comparison of Results from THMCB Modelling of Buffer, Backfill and Rock with Measured Data from Prototype Repository, Swedish Nuclear Fuel and Waste Management Company International Project Report, IPR-04-11 (2004). 

  37. A. Gens, A. Ledesma, P. Pusch, and L. Borgesson, "THMC Processes in Engineered Barriers: The Experience from Febex and Prototype Projects", Euradwaste' 04 Conference, Luxembourg (2004). 

  38. P.J. Cleall, T.A. Melhuish, and H.R. Thomas, "Modelling in the Three-dimensional Behaviour of a Prototype Nuclear Waste Repository", Eng. Geol., 85, 212-220 (2006). 

    상세보기 crossref

  39. H.R. Thomas and Y. He, "Modelling the Behaviour of Unsaturated Soil using an Elastic Constitutive Relationship", Geotechnique, 48, 589-603 (1998). 

    상세보기 crossref

  40. H.R. Thomas and P.J. Cleall, "Inclusion of Extensive Clay Behavior in Coupled Thermo Hydraulic Mechanical Models", Eng. Geol., 54, 93-108 (1999). 

    상세보기 crossref

  41. G.J. Chen and A. Ledesma, "Coupled Thermo-hydro-mechanical Modelling of the Full-scale In-situ Test Prototype Repository", Geotech. Geoenviron. Eng., 135, 121-132 (2009). 

    상세보기 crossref

  42. Swedish Nuclear Fuel and Waste Management Company, Aspo Hard Rock Laboratory Annual Report 2010, SKB Technical Report, TR-11-10 (2011). 

  43. Swedish Nuclear Fuel and Waste Management Company, Aspo Hard Rock Laboratory Annual Report 2015, SKB Technical Report, TR-16-10 (2016). 

  44. I. Gaus, B. Garitte, R. Senger, A. Gens, R. Vasconcelos, J-L. Garcia-Sineriz, T. Trick, K. Wieczorek, O. Czaikowski, K. Schuster, J.C. Mayor, M. Velasco, U. Kuhlmann, and M.V. Villar, The HE-E Experiment: Lay-out, Interpretation and THM Modelling, PEBS deliverable D2.2-11 and D3.2-2, NAB 14-053 (2014). 

  45. C-L. Zhang, T. Rothfuchs, N. Jockwer, K. Wieczorek, J. Dittrich, J. Muller, L. Hartwig, and M. Komischke, Thermal Effects on the Opalinus Clay, A Joint Heating Experiment of ANDRA and GRS at the Mont Terri URL (HE-D Project), GRS Final Report, GRS-224 (2007). 

  46. SCK/CEN. Geological Disposal: R&D for the Geological Disposal of Medium and High Level Waste in the Boom Clay (2008). 

  47. W. Bastiaens, The HADES Underground Research Facility (2007). 

  48. P.V. Marcke, P.X. Sillen, X.L. Li, G.J. Chen, A. Dizier, J. Leysen, I. Troullinos, J. Verstricht, and W. Bastiaens, "The PRACLAY Heater Test at URL HADES: Preparation of the Heater Switch-on", Clays in Natural and Engineered Barriers for Radioactive Waste Confinement, 6th International Conference, Brussels (2015). 

  49. W.J. Cho, J.S. Kim, C. Lee, S. Kwon, and J.W. Choi, "In-situ Experiments on the Performance of Near-field for Nuclear Waste Repository at KURT", Nucl. Eng. Design, 252, 278-288 (2012). 

    상세보기 crossref

  50. Korea Atomic Energy Reseach Institute, HLW Long-term Management System Development: Establishment of Infrastructure in KURT for In-situ Demonstration and Long-term Investigation of Repository System Performance, Korea Atomic Energy Research Institute Report, KAERI/RR-4201/2016 (2017). 

  51. O. Karnland, T. Sanden, L-E. Johannesson, T. Eriksen, M. Jansson, S. Wold, K. Pedersen, M. Motamedi, and B. Rosborg, Long-term Test of Buffer Material, Final Report on the Pilot Parcels, Swedish Nuclear Fuel and Waste Management Company Technical Report, TR-00-22 (2000). 

  52. Swedish Nuclear Fuel and Waste Management Company, Aspo Hard Rock Laboratory Annual Report 2000, SKB Technical Report, TR-01-10 (2001). 

  53. Swedish Nuclear Fuel and Waste Management Company, Aspo Hard Rock Laboratory Annual Report 2006, SKB Technical Report, TR-07-10 (2007). 

  54. Swedish Nuclear Fuel and Waste Management Company, Aspo Hard Rock Laboratory Annual Report 2007, SKB Technical Report, TR-08-10 (2008). 

  55. O. Karnland, S. Olsson, A. Dueck, M. Birgersson, U. Nilsson, T. Hernan-Hakansson, K. Pedersen, S. Nilsson, T. Eriksen, and B. Rosborg, Long-term Test of Buffer Material at the Aspo Hard Rock Laboratory, LOT Project, Final Report on the A2 Test Parcel, Swedish Nuclear Fuel and Waste Management Company Technical Report, TR-09-29 (2009). 

  56. O. Karnland, S. Olsson, T. Sanden, B. Falth, M. Jansson, T. Eriksen, K. Svardstrom, B. Rosborg, and A. Muurinen, Long-term Test of Buffer Material at the Aspo HRL, LOT Project Final Report on the A0 Test Parcel, Swedish Nuclear Fuel and Waste Management Company Technical Report, TR-09-31 (2011). 

  57. Swedish Nuclear Fuel and Waste Management Company, Aspo Hard Rock Laboratory Annual Report 2011, SKB Technical Report, TR-12-03 (2012). 

  58. Swedish Nuclear Fuel and Waste Management Company, Aspo Hard Rock Laboratory Annual Report 2012, SKB Technical Report, TR-13-03 (2013). 

  59. L-E. Johannesson, T. Sanden, M. Akesson, I. Barcena, and J. Garcia-Sineriz, Temperature Buffer Test, Installation of Buffer, Heaters and Instruments in the Deposition Hole, Swedish Nuclear Fuel and Waste Management Company Progress Report, P-12-02 (2010). 

  60. M. Akesson, Temperature Buffer Test, Dismantling Operation, Swedish Nuclear Fuel and Waste Management Company Progress Report, P-12-04 (2010). 

  61. L-E. Johannesson. Temperature Buffer Test, Measurements of Water Content and Density of the Excavated Buffer Material, Swedish Nuclear Fuel and Waste Management Company Progress Report, P-12-05 (2010). 

  62. M. Akesson, S. Olsson, A. Dueck, U. Nilsson, O. Karnland, L. Kiviranta, S. Kumpulainen, and J. Linden, Temperature Buffer Test, Hydro-mechanical and Chemical/Mineralogical Characterizations, Swedish Nuclear Fuel and Waste Management Company Progress Report, P-12-06 (2012). 

  63. H. Hokmark, A. Ledesma, T. Lassabatere, B. Falth, L. Borgesson, J. C. Robinet, N. Sellali, and P. Semete, "Modelling Heat and Moisture Transport in the ANDRA/SKB Temperature Buffer Test", Phys. Chem. Earth, Parts A/B/C 32, 753-766 (2007). 

    상세보기 crossref

  64. M. Akesson, Aspo Hard Rock Laboratory, Temperature Buffer Test, Evaluation Modeling- Field Test, Swedish Nuclear Fuel and Waste Management Company International Project Report, IPR-06-10 (2006). 

  65. M. Akesson, Aspo Hard Rock Laboratory, Temperature Buffer Test, Evaluation Modelling- Mock-up Test, Swedish Nuclear Fuel and Waste Management Company International Project Report, IPR-06-11 (2006). 

  66. M. Akesson, Aspo Hard Rock Laboratory, Temperature Buffer Test, Evaluation Modeling, TBT_3 Mock-up Test, Swedish Nuclear Fuel and Waste Management Company International Project Report, IPR-08-09 (2008). 

  67. M. Akesson, A. Jacinto, C. Gatabin, M. Sanchez, and A. Ledesma, "Bentonite THM Behaviour at High Temperatures: Experimental and Numerical Analysis", Geotechnique, 59, 307-318 (2009). 

    상세보기 crossref

  68. M. Akesson, D. Malmberg, L. Borgesson, J. Hernelind, A. Ledesma, and A. Jacinto, Temperature Buffer Test, Final THM Modelling, Swedish Nuclear Fuel and Waste Management Company Progress Report, P-12-07 (2012). 

  69. M. Akesson, Temperature Buffer Test, Final Report, Swedish Nuclear Fuel and Waste Management Company Technical Report, TR-12-04 (2012). 

  70. D. Svensson, A. Dueck, S. Olsson, T. Sanden, S. Lydmark, S. Jagevall, K. Pedersen, and S. Hansen, Alternative Buffer Material. Status of the Ongoing Laboratory Investigation of Reference Materials and Test Package 1, Swedish Nuclear Fuel and Waste Management Company Technical Report, TR-11-06 (2011). 

  71. D. Svensson, "Early Observations in a Large Scale 6 1/2 year Iron-bentonite Field Experiment ABM2 at Aspo Hard Rock Laboratory, Sweden", 50th Annual Meeting of Clay Mineralogical Society, Urbana-Champaign (2013). 

  72. P. Svensson and S. Hansen, "Redox Chemistry in Two Iron-bentonite Field Experiments at Aspo Hard Rock Laboratory, Sweden: an XRD and Fe K-edge XANES Study", Clays Clay Min., 61, 566-579 (2013). 

    상세보기 crossref

  73. E. Johansson, T. Siren, and K. Kemppainen, "ONKALO-Underground Rock Characterization Facility for In-situ Testing for Nuclear Waste Repository", 4th International Underground Research Laboratory Workshop, Montreal (2015). 

  74. R. Cuss, J. Harrington, and D. Noy, Large Scale Gas Injection Test (Lasgit) performed at the Aspo Hard Rock Laboratory, Summary Report 2008, Swedish Nuclear Fuel and Waste Management Company Technical Report, TR-10-38 (2010). 

  75. Swedish Nuclear Fuel and Waste Management Company, Aspo Hard Rock Laboratory Annual Report 2016, SKB Technical Report, TR-17-10 (2017). 

  76. P. Martensson, Aspo Hard Rock Laboratory, Concrete and Clay, Installation Report, Swedish Nuclear Fuel and Waste Management Company Progress Report, P-15-01 (2015). 

  77. C. Vogt, B. Lagerblad, K. Wallin, F. Baldy, and J-E. Jonasson, Low pH Self Compacting Concrete for Deposition Tunnel Plugs, Swedish Nuclear Fuel and Waste Management Company Report, R-09-07 (2009). 

  78. A. Boden and S. Pettersson, Development of Rock Bolt Grout and Shotcrete for Rock Support and Corrosion of Steel in Low-pH Cementious Materials, Swedish Nuclear Fuel and Waste Management Company, Report, R-11-08 (2011). 

  79. A. Mathern and J. Magnusson, System Design of Dome Plug, Experience of Low-pH Concrete Mix B200, Material Properties from Laboratory Tests and Full-scale Castings, Swedish Nuclear Fuel and Waste Management Company Progress Report, P-14-26 (2015). 

  80. A. Jenni, U. Mader, C. Lerouge, S. Gaboreau, and B. Schwyn, "In-situ Interaction between Different Concretes and Opalinus Clay", Phys. Chem. Earth, 70-71, 71-83 (2014). 

    상세보기 crossref

  81. J. Ludvigson, R. Nordqvist, L. Ekman, and K. Hansson, Aspo Hard Rock Laboratory, Backfill and Plug Test, Hydraulic Testing of Core Drilled Boreholes in the ZEDEX Drift, Swedish Nuclear Fuel and Waste Management Company International Project Report, IPR-09-01 (1999). 

  82. R. Goudarzi, L-E. Johannesson, and L. Borgesson, Backfill and Plug Test, Sensors Data Report (Period 990601-070101) Report No. 14, Swedish Nuclear Fuel and Waste Management Company International Project Report, IPR-08-02 (2008). 

  83. L-E. Johannesson, O. Kristensson, M. Akesson, P. Eriksson, and M. Hedin, Tests and Simulations of THM Processes Relevant for the Buffer Installation, Swedish Nuclear Fuel and Waste Management Company Progress Report, P-14-22 (2014). 

  84. B. Nyblad, D. Luterkort, and M. Lundqvist, Buffer Protection for the Installation Phase, Design and Testing, Swedish Nuclear Fuel and Waste Management Company Progress Report, P-13-51 (2014). 

  85. L. Borgesson and J. Hernelind, Modelling of Bentonite Block Compaction Swedish Nuclear Fuel and Waste Management Company Progress Report, P-14-10 (2014). 

  86. P. Eriksson, Basic Engineering of Buffer Production System, Swedish Nuclear Fuel and Waste Management Company Progress Report, P-14-11 (2014). 

  87. A. Arvidsson, P. Josefsson, T. Sanden, and M. Ojala, System Design of Backfill, Project Results, Swedish Nuclear Fuel and Waste Management Company Technical Report, TR-14-20 (2015). 

  88. C. Vogt, B. Lagerblad, K. Wallin, F. Baldy, and J-E. Jonasson, Low pH Self Compacting Concrete for Deposition Tunnel Plugs, Swedish Nuclear Fuel and Waste Management Company Report, R-09-07 (2009). 

  89. P. Grahm and R. Karlzen, System Design of Dome Plug, Experiences from Full-scale Wire Sawing of a Slot Abutment for the KBS-3V Deposition Tunnel Plug, Swedish Nuclear Fuel and Waste Management Company Report, R-14-24 (2015). 

  90. P. Grahm, R. Malm, and D, Eriksson, System Design and Full-scale Testing of the Dome Plug for KBS-3V Deposition Tunnels, Main Report, Swedish Nuclear Fuel and Waste Management Company Technical Report, TR-14-23 (2015). 

  91. H. Muller, T. Vogt, B. Garitte, S. Kohler, T. Sakaki, H-P. Weber, and T. Vietor, "The Full-Scale Emplacement Experiment- Implementation of a Multiple Heater Experiment at the Mont Terri URL", Clays in Natural and Engineered Barriers for Radioactive Waste Confinement, 6th International Conference, Brussels (2015). 

  92. S. Emsley, O. Olsson, L. Stenberg, H. J. Alheid, and S. Falls, ZEDEX- A Study of Damage and Disturbance from Tunnel Excavation by Blasting and Tunnel Boring, Swedish Nuclear Fuel and Waste Management Company Technical Report, TR 97-30 (1997). 

  93. B. Sabet, H. Shao, J. Autio, F. Elorza, I. Canamon, and J. Perez, "EDZ Assessment in the Febex II Project", in: Impact of Excavation Disturbed or Damaged Zone (EDZ) on the Performance of Radioactive Waste Geological Repositories, 137-142 (2005). 

  94. L. Liedtke, "Spread of Contaminants in Excavation Disturbed Zone Based on Results of Hydraulic In-situ Tests in Jointed Rock", in: Impact of Excavation Disturbed or Damaged Zone (EDZ) on the Performance of Radioactive Waste Geological Repositories, 157-162 (2005). 

  95. J. B. Martino and N. A. Chandler, "Excavation-induced Damage Studies at the Underground Research Laboratory", Int. J. Rock Mech. Min. Sci., 41, 1413-1426 (2004). 

    상세보기 crossref

  96. R. Pusch and R. Stanfors, "The Zone of Disturbance around Blasted Tunnel at Depth", Int. J. Rock Mech. Min. Sci. Geomech. Abstr., 29, 447-456 (1992). 

    상세보기 crossref

  97. K. Sugihara, "Geological Disposal of High-level Radioactive Waste and the Role of Rock Engineering", Int. of Japan. Com. Rock Mech., 5, 19-24 (2009). 

  98. T. Sato, T. Kikuchi, and K. Sugihara, "In-situ Experiments on an Excavation Disturbed Zone induced by Mechanical Excavation in Neogene Sedimentary Rock at Tono Mine", Central. Eng. Geol., 56, 97-108 (2000). 

    상세보기 crossref

  99. S. Kwon, C.S. Lee, S.J. Cho, S.W. Jeon, W.J. Cho, and J. Kim, "An Investigation of Excavation Damaged Zone at the KAERI Underground Research Tunnel", Tunn. Undergr. Space Technol., 24, 1-13 (2009). 

    상세보기 crossref

  100. W.J. Cho, J.S. Kim, C. Lee, S. Kwon, and J.W. Choi, "In-situ Experiments on the Performance of Near-field for Nuclear Waste Repository at KURT", Nucl. Eng. Des., 252, 278-288 (2012). 

    상세보기 crossref

  101. S. Mustonen, J. Norokallio, S. Mellanen, T. Lehtimaki, and E. Heikkinen, EDZ09 Project and Related EDZ Studies in ONKALO 2008-2010, POSIVA Working Report, 2010-27 (2010). 

  102. J.C. Andersson and A. Eng, Aspo Pillar Stability Experiment, Final Experiment Design, Monitored Data and Observations, Swedish Nuclear Fuel and Waste Management Company Report, R-05-02 (2005). 

  103. J.C. Andersson, Aspo Pillar Stability Experiment Final Report, Rock Mass Response to Coupled Mechanical Thermal Loading, Swedish Nuclear Fuel and Waste Management Company Technical Report, TR-07-01 (2007). 

  104. E. Johansson, T. Siren, M. Hakala, and P. Kantia, ONKALO POSE Experiment- Phase 1&2: Execution and Monitoring, POSIVA Working Report, 2012-60 (2014). 

  105. J. Valli, M. Hakala, T. Wanne, P. Kantia, and T. Siren, ONKALO POSE Experiment- Phase 3: Execution and Monitoring, POSIVA Working Report 2013-41 (2014). 

  106. GTS, The Material Corrosion Test (MaCoTe), http://www.grimsel.com/gts-phase-vi/macote-the-material-corrosion-test/macote. 2018. 1. 

  107. A.E, Bond, A.R. Hoch, G.D. Jones, A.J. Tomczyk, R.M. Wiggin, and W.J. Worraker, Assessment of a Spent Fuel Disposal Canister, Assessment Studies for a Copper Canister with Cast Steel Inner Component, Swedish Nuclear Fuel and Waste Management Company Technical Report, TR 97-19 (1997). 

  108. N.R. Smart, A.P. Rance, and P.A.H. Fennell, Expansion due to the Anaerobic Corrosion of Iron, Swedish Nuclear Fuel and Waste Management Company Technical Report, TR-06-41 (2006). 

  109. N.R. Smart and A.P. Rance, Miniature Canister Corrosion Experiment- Results of Operations to May 2008, Swedish Nuclear Fuel and Waste Management Company Technical Report, TR-09-20 (2009). 

  110. N.R. Smart, A.P. Rance, B. Reddy, P. Fennell, and R.J. Winsley, Analysis of SKB MiniCan Experiment 3, Swedish Nuclear Fuel and Waste Management Company Technical Report, TR-12-09 (2012). 

  111. N.R. Smart, S. Rose, D. Nixon, and A. Rance, Metallographic Analysis of SKB MiniCan Experiment 3, Swedish Nuclear Fuel and Waste Management Company Report, R-13-35 (2013). 

  112. N.R. Smart, B. Reddy, D. Nixon, A. Rance, and A.J. Johansson, Miniature Canister (MiniCan) Corrosion Experiment, Progress Report for 2008-2013, Swedish Nuclear Fuel and Waste Management Company Progress Report, P-14-19 (2015). 

  113. A.J. Johansson, C. Lilja, L. Sjogren, A. Gordon, and L. Johansson, "Insights from Post-test Examination of Three Packages from the MiniCan Test Series of Copper-cast Iron Canisters for Geological Disposal of Spent Nuclear Fuel: Impact of the Presence and Density of Bentonite Clay", Corros. Eng. Sci. Tech., 52, 54-60 (2017). 

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