DOI QR코드

DOI QR Code

A Numerical Analysis to Estimate Disposal Spacing and Rock Mass Condition for High Efficiency Repository Based on Temperature Criteria of Bentonite Buffer

벤토나이트 완충재 설계 기준 온도에 따른 고효율 처분시스템 처분 간격 및 암반 조건 산정을 위한 수치해석적 연구

  • Received : 2021.08.18
  • Accepted : 2021.08.26
  • Published : 2021.08.31

Abstract

This study conducts coupled thermo-hydro-mechanical numerical modeling to investigate the maximum temperature and conditions for securing mechanical stability of the high-level radioactive waste repository when temperature criteria of bentonite buffer are 100℃ and 125℃, respectively. In case of temperature criterion of buffer as 100℃, the maximum temperatures at the interface between canister and buffer are calculated to be 99.4℃ and 99.8℃, respectively for a case with disposal tunnel spacing of 40 m and deposition hole spacing of 5.5 m and for the other case with disposal tunnel spacing of 30 m and deposition hole spacing of 6.5 m. In case of temperature criterion of buffer as 125℃, spacings of disposal tunnel and deposition hole could be decreased to 30 m and 4.5 m, respectively, which reduces the disposal area up to 55% compared to the disposal area of KRS+. According to analysis of mechanical stability for various disposal spacings, RMR of rock mass for KRS+ should be larger than 72.4 which belongs to good rock in RMR classification to prevent failure of rock mass. As disposal spacing is decreased, required RMR of rock mass is increased. In order to prevent failure of rock mass for a case with disposal tunnel spacing of 30 m and deposition hole spacing of 4.5 m, RMR larger than 87.3 is needed. However, mechanical stability of the repository is secured for all cases with RMR over 75 considering the enhancement of rock strength due to confining stress induced by swelling of the bentonite buffer and backfill.

본 연구에서는 열-수리-역학적 복합거동 수치해석을 활용하여 국내 고준위방사성폐기물 처분장의 완충재의 설계 기준 온도가 100℃ 및 125℃인 경우, 처분 간격에 따른 처분시스템의 최고 온도를 계산하고, 역학적 안정성을 확보하기 위한 암반의 조건을 도출하였다. 완충재의 설계 기준 온도를 현재와 같이 100℃로 유지할 때, 처분터널 간격이 40 m, 처분공 간격이 5.5 m인 경우와 처분터널 간격이 30 m, 처분공 간격이 6.5 m인 경우, 처분용기와 완충재가 접하는 점에서 최고 온도가 각각 99.4℃ 및 99.8℃로 계산되었다. 완충재의 설계 기준 온도를 125℃로 향상시킨 경우, 처분터널 간격을 30 m, 처분공 간격을 4.5 m까지 감소시켜 처분 면적을 KRS+ 기반 처분시스템 대비 55%까지 감소시킬 수 있었다. 다양한 처분 간격에 대해 암반에서의 역학적 안정성을 평가한 결과, 암반파괴가 발생하지 않기 위해서는 KRS+ 기반 처분시스템은 암반의 RMR 분류법의 Good rock에 해당하는 RMR 72.4 이상의 조건이어야 했다. 처분 간격이 감소할수록 암반의 RMR이 더 높아야 했으며, 처분터널 간격 30 m, 처분공 간격 4.5 m인 경우에는 RMR 87.3 이상이 되어야 암반의 파괴를 방지할 수 있었다. 그러나, 처분 이후 지하수 유입 시 벤토나이트 완충재 및 뒤채움재의 팽윤에 따른 구속압에 의한 암반 강도의 증가를 고려하면, 해석을 수행한 모든 처분 간격에 대해 암반의 RMR이 75 이상이면 역학적 안정성을 확보할 수 있었다.

Keywords

Acknowledgement

이 논문은 2021년도 정부(과학기술정보통신부)의 재원으로 고준위폐기물관리차세대혁신기술개발사업의 지원(2021M2E3A2041312)과 사용후핵연료관리핵심기술개발사업단 및 한국연구재단의 지원(2021M2E1A1085193)을 받아 수행된 연구사업입니다.

References

  1. Allen, C.C., Lane, D.L., Palmer, R.A., and Johnston, R.G., 1984, MRS Online Proceedings Library, 26, 105-112.
  2. Alonso, J. and 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).
  3. Aydan, O, Akagi, T., and Kawamoto, T., 1993, The squeezing potential of rocks around tunnels; theory and prediction, Rock Mechanics and Rock Engineering, 26(2), 137-163. https://doi.org/10.1007/BF01023620
  4. Aydan, O. and Dalgic, S., 1998, Prediction of deformation behavior of 3-lanes Bolu tunnels through squeezing rocks of Nurth Anatolian fault zone (NAFZ), In: Proceedings of the Regional Symposium on Sedimentary Rock Engineering, Taipei, Taiwan, 228-233.
  5. Aydan, O. and Kawamoto, T., 2001, The stability assessment of a large underground opening at great depth, In: Proceedings of the 17th International Mining Congress and Exhibition of Turkey (IMCET2001), Ankara ,Turkey, June 2001, 277-288.
  6. Bieniawski, Z. T., 1988, The rock mass rating (RMR) system (geomechanics classification) in engineering practice in Rock Classification Systems for Engineering Purposes, ASTM International, 17-34.
  7. Bieniawski, Z.T., 1989, Engineering rock mass classifications, New York, Wiley.
  8. Cho, W.J. and Kim, G.Y., 2016, Reconsideration of thermal criteria for Korean spent fuel repository, Annals of Nuclear Energy, 88, 73-82. https://doi.org/10.1016/j.anucene.2015.09.012
  9. Cho, W.J., 2019, Bentonite - Barrier material for radioactive waste disposal, KAERI/GP-535/2019, Korea Atomic Energy Research Institute.
  10. Couture, R.A., 1985, Steam rapidly reduces the swelling capacity of bentonite, Nature, 318, 50-52. https://doi.org/10.1038/318050a0
  11. Graf, R. and Filbert, W., 2006, Disposal of spent fuel from German nuclear power plants - Paper work or technology, Topseal Conference, 17-20, September, Olkiluoto, Finland.
  12. Itasca, 2012, FLAC3D, Fast Lagrangian Analysis of Continua in 3 Dimensions, Version 5.0. Itasca Consulting Group, Minneapolis, Minnesota, Itasca.
  13. Jeanne, P., Rutqivst, J., Dobson, P.F., Walters, M., Hartline, C., and Garcia, J., 2014, The impacts of mechanical stress transfers caused by hydromechanical and thermal processes on fault stability during hydraulic stimulation in a deep geothermal reservoir, International Journal of Rock Mechanics and Mining Sciences, 72, 149-163. https://doi.org/10.1016/j.ijrmms.2014.09.005
  14. JNC, 2000, H12: Project to establish the scientific and technical basis for HLW disposal in Japan, JNC TN1410 2000-003, Japan Nuclear Cycle Development Institute.
  15. Johnson, L.H., Tait, J.C., Shoesmith, D.W., Crosthwaite, J.L., and Gray, M.N., 1994, The disposal of Canada's nuclear fuel waste: Engineerred barriers alternatives, AECL-10718, COG-93-8, Atomic Energy of Canada Limited.
  16. Kim, G.W., 1993, Revaluation of geomechanics classifications of rock masses, In: Geotechnical Engineering and Tunneling Technology, Korean Geotechnical Society Spring 93 National Conference, Seoul Korea.
  17. Kim, J.S., Cho, W.J., Park, S., Kim, G.Y., and Baik, M.H., 2019, A review on the design require of temperature in high-level nuclear waste disposal system: based on bentonite buffer, Journal of Korean Tunnelling and Underground Space Association, 21(5), 587-609. https://doi.org/10.9711/KTAJ.2019.21.5.587
  18. Kim, K.I., Lee, C., and Kim, J.S., 2021, A Numerical Study of the Performance Assessment of Coupled Thermo-Hydro-Mechanical (THM) Processes in Improved Korean Reference Disposal System (KRS+) for High-Level Radioactive Waste, Tunnel and Underground Space, 31(4), 221-242. https://doi.org/10.7474/TUS.2021.31.4.221
  19. Lee, C., 2012, Characterization of thermal-mechanical behavior of rock mass in the excavation damaged zone at KURT, Ph.D. dissertation, Seoul National University, Korea.
  20. Lee, C., Cho W.J., Lee J., Kim G.Y., 2019a, Numerical analysis of coupled thermo-hydro-mechanical (THM) behavior at Korean reference disposal system (KRS) using TOUGH2-MP/FLAC3D simulator, Journal of Nuclear Fuel Cycle and Waste Technology, 17(2), 183-202. https://doi.org/10.7733/jnfcwt.2019.17.2.183
  21. Lee, C., Lee, J., Park, S., Kwon, S., Cho, W.J., and Kim, G.Y., 2020a, Numerical analysis of coupled thermo-hydro-mechanical behavior in single- and multi-layer repository concepts for high-level radioactive waste disposal, Tunnelling and Underground Space Technology, 103, 103452. https://doi.org/10.1016/j.tust.2020.103452
  22. Lee, J., Cho, D., Choi, H., and Choi, J., 2007, Concept of a Korean reference disposal system for spent fuels, Journal of Nuclear Science and Technology, 44(12), 1565-1573. https://doi.org/10.3327/jnst.44.1565
  23. Lee, J., Kim, I., Ju, H.J., Choi, H., and Cho, D., 2020b, Proposal of an improved concept design for the deep geological disposal system of spent nuclear fuel in Korea. Journal of Nuclear Fuel Cycle and Waste Technology, 18, 1-19.
  24. Lee, J., Lee, C., and Kim, G.Y., 2016, Development of TOUGH2-MP/FLAC3D simulator for the coupled thermalhydraulic-mechanical analysis in porous media, KAERI Technical Report, KAERI/TR-6737/2016, Korea Atomic Energy Research Institute.
  25. Martin, P.L. and 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.
  26. NAGRA, 2002, Demonstration of disposal feasibility for spent fuel, vitrified high-level waste and long-lived intermediate-level waste (Entsorgungsnachweis), NAGRA Technical Report 02-05, Natioanl Cooperative for the Disposal of Radioactive Waste.
  27. POSIVA and SKB, 2017, Safety functions, performance targets and technical design requirements for a KBS-3V repository, Posiva SKB report 01, Swedish Nuclear Fuel and Waste Management Co.
  28. POSIVA, 2008, Quality assurance of the bentonite material, POSIVA Working Report 2008-33.
  29. Pruess, K., Oldenburg, C., and Moridis, G., 2011, TOUGH2 user's guide, version 2, Lawrence Berkeley National Laboratory Report LBNL-43134, Berkeley, CA, USA.
  30. Pusch, R., Bluemling, P., and Johnson, L., 2003, Performance of strongly compressed MX-80 pellets under repository-like conditions, Applied Clay Science, 23, 239-244. https://doi.org/10.1016/S0169-1317(03)00108-X
  31. Rutqvist, J., 2020, Thermal management associated with geologic disposal of large spent nuclear fuel canisters in tunnels with thermally engineered backfill, Tunnelling and Underground Space Technology, 102, 103454. https://doi.org/10.1016/j.tust.2020.103454
  32. Rutqvist, J., Chijimatsu, M., Jing, L., Millard, A., Nguyen, T.S., Rejeb, A., Sugita, Y., and Tsang, C.F., 2005, A numerical study of THM effects on the near-field safety of a hypothetical nuclear waste repository - BMT1 of the DECOVALEX III project. Part 3: Effects of THM coupling in sparsely fractured rocks, International Journal of Rock Mechanics and Mining Sciences, 42, 745-755. https://doi.org/10.1016/j.ijrmms.2005.03.012
  33. Rutqvist, J., Wu, Y.S., Tsang, C.F., and Bodvarsson, G., 2002, A modeling approach for analysis of coupled multiphase fluid flow, heat transfer, and deformation in fractured porous rock, International Journal of Rock Mechanics and Mining Sciences 39, 429-442. https://doi.org/10.1016/S1365-1609(02)00022-9
  34. SKB, 2003, Thermal dimensioning of the deep repository, SKB Technical Report TR-03-09, Swedish Nuclear Fuel and Waste Management Co.
  35. SKB, 2010, Choice of method - Evaluation of strategies and systems for disposal of spent nuclear fuel, SKB report, SKB P-10-47, Swedish Nuclear Fuel and Waste Management Co.
  36. 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.
  37. Sunwoo, C., Ryu, D.W., Kim, H.M., and Kim, K.S., 2011, Study on the geotechnical characteristics of granite in Korea and their correlation with rock classification method, Tunnel and Underground Space, 21(3), 205-215. https://doi.org/10.7474/TUS.2011.21.3.205
  38. Tohata, I., Kuntiwattanakul, P., Oishi, K., and Takeuchi, N., 1998, Effect of elevated temperature on mechanical behaviour of clays, Tsuchi To Kiso, 46(10). 27-30 (in Japanese).
  39. Trueman, R., 1988, An evaluation of strata support techniques in dual life gateroads, Ph.D. Thesis, University of Wales, Cardiff, UK.
  40. Wersin, P., Johnson, L.H., and McKinley, I.G., 2007, Performance of the bentonite barrier at temperatures beyond 100℃: A critical review, Physics and Chemistry of the Earth, 32, 780-788. https://doi.org/10.1016/j.pce.2006.02.051
  41. Wickham, S.M., 2008, Evolution of the near-field of the ONDRAF/NIRAS repository concept for category C wastes, NIROND-TR Report 2007-07E.
  42. Zhang, K., Wu, Y.S., Pruess, K., 2008, User's guide for TOUGH2-MP - A massively parallel version of the TOUGH2 code, Lawrence Berkeley National Laboratory Report LBNL-315E, Berkeley, CA, USA.