Browse > Article
http://dx.doi.org/10.7733/jnfcwt.2018.16.2.137

Validation of Performance of Engineered Barriers in a Geological Repository: Review of In-Situ Experimental Approach  

Cho, Won-Jin (Korea Atomic Energy Research Institute)
Kim, Geon Young (Korea Atomic Energy Research Institute)
Publication Information
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT) / v.16, no.2, 2018 , pp. 137-164 More about this Journal
Abstract
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 in-situ experiments conducted in an underground research laboratory. This article provides a review of the major in-situ experiments that have been carried out over the past several decades at underground research laboratories around the world to validate the performance of engineered barriers of a repository, as well as their results. In-situ experiments to study the coupled thermal-hydraulic-mechanical behavior of the engineered barrier system used to simulate the post-closure performance of the repository are analyzed as a priority. In addition, in-situ experiments to investigate the performance of the buffer material under a real repository environment have been reviewed. State-of-the art in-situ validations of the buffer-concrete interaction, and the installation of the buffer, backfill and plug, as well as characterization of the near-field rock and the corrosion of the canister materials are, also performed.
Keywords
In-situ experiment; Engineered barriers; Geological repository; Validation; Demonstration;
Citations & Related Records
연도 인용수 순위
  • Reference
1 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).
2 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).   DOI
3 H.R. Thomas and Y. He, "Modelling the Behaviour of Unsaturated Soil using an Elastic Constitutive Relationship", Geotechnique, 48, 589-603 (1998).   DOI
4 H.R. Thomas and P.J. Cleall, "Inclusion of Extensive Clay Behavior in Coupled Thermo Hydraulic Mechanical Models", Eng. Geol., 54, 93-108 (1999).   DOI
5 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).   DOI
6 Swedish Nuclear Fuel and Waste Management Company, Aspo Hard Rock Laboratory Annual Report 2010, SKB Technical Report, TR-11-10 (2011).
7 Swedish Nuclear Fuel and Waste Management Company, Aspo Hard Rock Laboratory Annual Report 2015, SKB Technical Report, TR-16-10 (2016).
8 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).
9 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).
10 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).
11 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).
12 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).
13 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).
14 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).
15 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).
16 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).
17 National Cooperative for the Disposal of Radioactive Waste, "The Mont Terri Rock Laboratory", NAGRA Bulletin, 34, 24-35 (2002).
18 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).
19 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.
20 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).
21 Swedish Nuclear Fuel and Waste Management Company Aspo Hard Rock Laboratory- A Unique Place for Experiments and Research (2016).
22 Department of Energy, Yucca Mountain Science and Engineering Report, U. S. Department of Energy Report, DOE/RW-0539-1 (2002).
23 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).   DOI
24 SCK/CEN. Geological Disposal: R&D for the Geological Disposal of Medium and High Level Waste in the Boom Clay (2008).
25 W. Bastiaens, The HADES Underground Research Facility (2007).
26 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).
27 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).
28 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).
29 Department of Energy, Department of Energy FY 2019 Congressional Budget Request, U. S. Department of Energy Report, DOE/CF-0141 (2018).
30 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).   DOI
31 POSIVA. ONKALO URL Homepage, Accessed Jan. 2018, Available from: http://www.posiva.fi/englanti/; ONKALO Situation.
32 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).   DOI
33 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).
34 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).   DOI
35 Swedish Nuclear Fuel and Waste Management Company, Aspo Hard Rock Laboratory Annual Report 2000, SKB Technical Report, TR-01-10 (2001).
36 Swedish Nuclear Fuel and Waste Management Company, Aspo Hard Rock Laboratory Annual Report 2006, SKB Technical Report, TR-07-10 (2007).
37 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).   DOI
38 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).
39 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).   DOI
40 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).   DOI
41 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).
42 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).
43 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).
44 TRW, Characterization of the Drift Scale Test Block, TRW Environmental Safety Systems Report, RADD00000-01717-5705-00001 Rev. 00 (1997).
45 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).
46 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).
47 TRW, Drift Scale Test Design and Forecast Results, TRW Environmental Safety Systems Report, BAB000000-01717-4600-00007 Rev. 00 (1997).
48 Itasca Consulting Group, FLAC-Fast Lagrangian Analysis of Continua, Version 4.0 (2000).
49 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).
50 Swedish Nuclear Fuel and Waste Management Company, Aspo Hard Rock Laboratory Annual Report 2007, SKB Technical Report, TR-08-10 (2008).
51 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).
52 Swedish Nuclear Fuel and Waste Management Company, Aspo Hard Rock Laboratory Annual Report 2011, SKB Technical Report, TR-12-03 (2012).
53 Swedish Nuclear Fuel and Waste Management Company, Aspo Hard Rock Laboratory Annual Report 2012, SKB Technical Report, TR-13-03 (2013).
54 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).
55 M. Akesson, Temperature Buffer Test, Dismantling Operation, Swedish Nuclear Fuel and Waste Management Company Progress Report, P-12-04 (2010).
56 French Atomic Energy Commission, CASTEM, An Objective Oriented Finite Element Method Framework (2000).
57 E. Johansson, T. Siren, M. Hakala, and P. Kantia, ONKALO POSE Experiment- Phase 1&2: Execution and Monitoring, POSIVA Working Report, 2012-60 (2014).
58 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).
59 K. Pruess, C. Oldenburg, and G. Moridis. TOUGH2 User's Guide, Version 2.0, Lawrence Berkeley National Laboratory Report, LBNL-43134 (1999).
60 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).   DOI
61 P.L. Martin and J.M. Barcala, "Large Scale Buffer Material Test: Mock-up Experiment at CIEMAT", Eng. Geol., 81, 298-316 (2005).   DOI
62 Empresa Nacional de Residuos Radiactivos S.A., Full-scale Engineered Barriers Experiment, Updated Final Report 1994-2004, ENRESA Technical Publication, 05-0/2006 (2006).
63 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).
64 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).
65 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).
66 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).
67 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).
68 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).
69 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).   DOI
70 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).
71 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).
72 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).
73 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).
74 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).
75 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).   DOI
76 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).
77 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).   DOI
78 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).
79 GTS, The Material Corrosion Test (MaCoTe), http://www.grimsel.com/gts-phase-vi/macote-the-material-corrosion-test/macote. 2018. 1.
80 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).
81 DECOVALEX-2019, Accessed Jan. 2018, Available from: http://decovalex.org, 2018. 1.
82 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).
83 M. Akesson, Temperature Buffer Test, Final Report, Swedish Nuclear Fuel and Waste Management Company Technical Report, TR-12-04 (2012).
84 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).
85 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).   DOI
86 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).
87 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).
88 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).
89 Swedish Nuclear Fuel and Waste Management Company, Aspo Hard Rock Laboratory Annual Report 2013, SKB Technical Report, TR-14-17 (2014).
90 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).
91 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).   DOI
92 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).
93 Swedish Nuclear Fuel and Waste Management Company, Aspo Hard Rock Laboratory Annual Report 2014, SKB Technical Report, TR-15-10 (2015).
94 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).
95 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).
96 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).
97 P. Martensson, Aspo Hard Rock Laboratory, Concrete and Clay, Installation Report, Swedish Nuclear Fuel and Waste Management Company Progress Report, P-15-01 (2015).
98 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).
99 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).
100 Swedish Nuclear Fuel and Waste Management Company, Aspo Hard Rock Laboratory Annual Report 2016, SKB Technical Report, TR-17-10 (2017).
101 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).
102 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).
103 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).
104 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).
105 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).
106 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).
107 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).   DOI
108 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).
109 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).
110 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).
111 L. Borgesson and J. Hernelind, Modelling of Bentonite Block Compaction Swedish Nuclear Fuel and Waste Management Company Progress Report, P-14-10 (2014).
112 P. Eriksson, Basic Engineering of Buffer Production System, Swedish Nuclear Fuel and Waste Management Company Progress Report, P-14-11 (2014).
113 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).