Browse > Article
http://dx.doi.org/10.5516/NET.06.2012.015

AN ANALYSIS OF THE THERMAL AND MECHANICAL BEHAVIOR OF ENGINEERED BARRIERS IN A HIGH-LEVEL RADIOACTIVE WASTE REPOSITORY  

Kwon, S. (Department of Energy Resources Engineering, Inha University)
Cho, W.J. (Korea Atomic Energy Research Institute)
Lee, J.O. (Korea Atomic Energy Research Institute)
Publication Information
Nuclear Engineering and Technology / v.45, no.1, 2013 , pp. 41-52 More about this Journal
Abstract
Adequate design of engineered barriers, including canister, buffer and backfill, is important for the safe disposal of high-level radioactive waste. Three-dimensional computer simulations were carried out under different condition to examine the thermal and mechanical behavior of engineered barriers and rock mass. The research looked at five areas of importance, the effect of the swelling pressure, water content of buffer, density of compacted bentonite, emplacement type and the selection of failure criteria. The results highlighted the need to consider tensile stress in the outer shell of a canister due to thermal expansion of the canister and the swelling pressure from the buffer for a more reliable design of an underground repository system. In addition, an adequate failure criterion should be used for the buffer and backfill.
Keywords
Buffer; Backfill; HLW Disposal; Thermal-mechanical; Canister; Deposition Hole;
Citations & Related Records
Times Cited By KSCI : 5  (Citation Analysis)
연도 인용수 순위
1 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   DOI   ScienceOn
2 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.
3 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).   DOI   ScienceOn
4 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).   DOI   ScienceOn
5 KAERI, "Advanced Nuclear Fuel Cycle," KAERI Newsletter (2008)
6 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).   과학기술학회마을   DOI   ScienceOn
7 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).
8 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).   과학기술학회마을
9 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).   과학기술학회마을
10 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).   과학기술학회마을
11 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).   과학기술학회마을
12 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).   과학기술학회마을
13 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).   DOI   ScienceOn
14 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).   과학기술학회마을   DOI   ScienceOn
15 R.Pusch, "The performance of clay barriers in repositories for high-level radioactive waste," Nuclear Engineering and Technology, vol.38, pp.484-488(2006).
16 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)   과학기술학회마을
17 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).   DOI   ScienceOn
18 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).   DOI   ScienceOn
19 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).
20 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).
21 Itasca, FLAC3D user's manual.
22 SKB, "The Stripa project, Annual report 1985," Swedish Nuclear Fuel and Waste Management Company (SKB), Technical report 86-20 (1986).