참고문헌
- F.Dupray, B.Francois and L.Laloui, "Analysis of the FEBEX multi-barrier system including thermoplasticity of unsaturated bentonite," International Journal for Numerical and Analytical Methods in Geomechanics, doi: 10.1002/nag.1103
- O.Karnland, S.Olsson, T.Sanden, B.Falth, M.Jansson, T.E. Eriksen, K.Svardström, B.Rosborg and A.Muurinen, Long term test of buffer material at the Aspo HRL, LOT project, SKB TR-09-31.
-
E.Alonso and C.Hoffmann, "Modelling the field behaviour of a granular expansive barrier," Physics and Chemistry of the Earth, vol.32, pp.
$850^{\circ}(C)865$ (2007). https://doi.org/10.1016/j.pce.2006.04.039 - J. Lee, D. Cho, H. Choi and J. Choi, "Concept of a Korean reference disposal system for spent fuels," J. Nucl. Sci. Technol., vol.44, 1565-1573 (2007). https://doi.org/10.1080/18811248.2007.9711407
- KAERI, "Advanced Nuclear Fuel Cycle," KAERI Newsletter (2008)
- J.Yoon and J.Ahn, "A systems assessment for the Korean Advanced nuclear fuel cycle concept from the perspective of radiological impact," Nuclear Engineering and Technology, vol.42, pp.17-36(2009). https://doi.org/10.5516/NET.2010.42.1.017
- W.J.Cho, J.O.Lee and C.H.Kang, "A compilation and evaluation of thermal and mechanical properties of bentonitebased buffer materials for a high-level waste repository," J.of the Korean Nuclear Society, vol.34, pp.90-103(2002).
- W.J.Cho, J.O.Lee and S.Kwon, "A correlation to predict the thermal conductivity of buffer and backfill material for a high-level waste repository," Tunnel & underground space, vol. 20, pp. 284-291(2010).
- J.O.Lee, W.J.Cho and S.Kwon, "Thermal-hydro-mechanical Properties of Reference Bentonite Buffer for a Korean HLW Repository," Tunnel & Underground space, vol. 21, pp. 264-273(2011).
- J.O.Lee, W.J.Cho, P.S.Hahn and H.H.Park, "A study on the hydraulic properties of domestic clay/crushed rock mixture for the backfill material in a radioactive waste repository," J.of Korean Nuclear Society, vol.26, pp.54-62(1994).
- W.J.Cho, J.O.Lee and C.H.Kang, "Hydraulic conductivity of bentonite-sand mixture for a potential backfill material for a high-level radioactive waste repository," J.of the Korean Nuclear Society, vol.32, pp.495-503(2000).
- J.H.Park, J.E.Kuh and S.Kwon, "Thermal analysis of high level radioactive waste repository using a large model," J.of the Korean Nuclear Society, vol.32, pp.244-253(2000).
- S.Kwon and J.W.Choi, "Thermo-mechanical Stability Analysis for a Multi-level Radioactive Waste Disposal Concept," Geotechnical and Geological Engineering, vol. 24, pp.361-377(2006). https://doi.org/10.1007/s10706-004-7935-5
- J.Kim, Y.K.Koh, D.S.Bae and J.W.Choi, "Depth and layout optimizations of a radioactive waste repository in a discontinuous rock mass based on a thermo-mechanical model," Nuclear engineering and technology, vol.40, pp.429-438 (2008). https://doi.org/10.5516/NET.2008.40.5.429
- R.Pusch, "The performance of clay barriers in repositories for high-level radioactive waste," Nuclear Engineering and Technology, vol.38, pp.484-488(2006).
- W.J.Cho, J.O.Lee and S.Kwon, "Thermal Conductivity of Compacted Bentonite and Bentonite-Sand Mixture," J. of the Korean Radioactive Waste Society, vol.6(2), pp. 101- 109(2008)
- W.J.Cho, J.O.Lee and K.S.Chun, "The temperature effects on hydraulic conductivity on compacted bentonite," Applied Clay Science, vol.14, pp.47-58(1999). https://doi.org/10.1016/S0169-1317(98)00047-7
- 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(1999).
- B.Y.Park, D.S.Bae, C.S.Kim, K.S.Kim and Y.K.Ko, "Evaluation of the basic mechanical and thermal properties of deep crystalline rocks," KAERI/TR-1828/2001(2001).
- A.F.Fossum, "Effective elastic properties for a randomly jointed rock mass," Int. J. Rock Mech. Min. Sci., vol.22(6), pp.467-470(1985). https://doi.org/10.1016/0148-9062(85)90011-7
- Itasca, FLAC3D user's manual.
- SKB, "The Stripa project, Annual report 1985," Swedish Nuclear Fuel and Waste Management Company (SKB), Technical report 86-20 (1986).
피인용 문헌
- An assessment of strontium sorption onto bentonite buffer material in waste repository vol.24, pp.9, 2017, https://doi.org/10.1007/s11356-017-8536-1