Acknowledgement
This work was supported by the Institute for Korea Spent Nuclear Fuel (iKSNF) and National Research Foundation of Korea (NRF) grant funded by the Korea government (Ministry of Science and ICT, MSIT) (NRF-2021M2E1A1085185).
References
- IAEA, IAEA Safety Standards for Protecting People and the Environment - Geological Disposal Facilities for Radioactive Waste, IAEA, 2011, p. 1. Specific Safety Guide No. SSG-14.
- SKBF/KBS, Final Storage of Spent Nuclear Fuel - KBS-3: Summary, SKBF/KBS, 1983.
- P.A. Witherspoon, G.S. Bodvarsson, Geological Challenges in Radioactive Waste Isolation - Fourth Worldwide Review, Lawrence Berkeley Natl. Lab., 2006. LBNL-59808.
- IAEA, IAEA Safety Standards for Protecting People and the Environment - the Safety Case and Safety Assessment for the Disposal of Radioactive Waste, IAEA, 2012, pp. 4-5. Specific Safety Guide No. SSG-23.
- K. Ikonen, Thermal Analyses of Spent Nuclear Fuel Repository, Posiva Oy, 2003. POSIVA 2003-04.
- X. Pintado, E. Rautioaho, Thermal-hydraulic Modelling of Buffer and Backfill, Posiva Oy, 2013. POSIVA 2012-48.
- E. Toprak, N. Mokni, S. Olivella, X. Pintado, Thermo-Hydro-Mechanical Modelling of Buffer - Synthesis Report, Posiva Oy, 2013, p. 2047. POSIVA 2012.
- A. Idiart, F. Maia, D. Arcos, Geochemical Evaluation of the Near-Field for Future HLW Repository at Olkiluoto, Posiva Oy, 2013. POSIVA 2013-05.
- Posiva Oy, Safety Case for the Disposal of Spent Nuclear Fuel at Olkiluoto - Synthesis 2012, Posiva Oy, 2012. POSIVA 2012-12.
- J.-W. Kim, D.-K. Cho, N.-Y. Ko, J. Jeong, M.-H. Baik, Model development for risk-based safety assessment of a geological disposal system of radioactive wastes generated by pyroprocessing of pressurized water reactor spent fuel in Korea, Nucl. Technol. 203 (2018) 1-16. https://doi.org/10.1080/00295450.2018.1426331
- D. Clayton, G. Freeze, T. Hadgu, E. Hardin, J. Lee, J. Prouty, R. Rogers, W.M. Nutt, J. Birkholzer, H.H. Liu, L. Zheng, S. Chu, Generic Disposal System Modeling - Fiscal Year 2011 Progress Report: Fuel Cycle Research & Development, Sandia Natl. Lab., SAND2011-5828.
- R.T. Mills, C. Lu, P.C. Lichtner, G.E. Hammond, Simulating subsurface flow and transport on ultrascale computers using PFLOTRAN, J. Phys. Conf. 78 (2007) 12051. https://doi.org/10.1088/1742-6596/78/1/012051
- A. Nardi, A. Idiart, P. Trinchero, L.M. de Vries, J. Molinero, Interface COMSOLPHREEQC (iCP), an efficient numerical framework for the solution of coupled multiphysics and geochemistry, Comput. Geosci. 69 (2014) 10-21. https://doi.org/10.1016/j.cageo.2014.04.011
- J. Carrayrou, R. Mose, P. Behra, Operator-splitting procedures for reactive transport and comparison of mass balance errors, J. Contam. Hydrol. 68 (2004) 239-268. https://doi.org/10.1016/S0169-7722(03)00141-4
- R.P. Rechard, C.T. Stockman, Waste degradation and mobilization in performance assessments for the Yucca Mountain disposal system for spent nuclear fuel and high-level radioactive waste, Reliab. Eng. Syst. Saf. 122 (2014) 165-188. https://doi.org/10.1016/j.ress.2013.06.028
- M. Amaku, P.R. Pascholati, V.R. Vanin, Decay chain differential equations: solution through matrix algebra, Comput. Phys. Commun. 181 (2010) 21-23. https://doi.org/10.1016/j.cpc.2009.08.011
- D.L. Parkhurst, C.A.J. Appelo, Description of input and eamples for PHREEQC version 3 - a computer program for speciation, batch-reaction, one-dimensional transport, and inverse geochemical calculations, U.S.Geol. Surv. Tech.- Methods (2013) 497.
- J. Lee, H. Kim, I. Kim, H. Choi, D. Cho, Analyses on thermal stability and structural integrity of the improved disposal systems for spent nuclear fuels in Korea, J.Nucl. Fuel Cycle.Waste Treat. 18 (S) (2020) 21-36. https://doi.org/10.7733/jnfcwt.2020.18.S.21
- C. Lee, J. Lee, S. Park, S. Kwon, W.-J. Cho, G.Y. Kim, Numerical analysis of coupled thermo-hydro-mechanical behavior in single and multi-layer repository concepts for high-level radioactive waste disposal, Tunn. Undergr. Space Technol. 103 (2020), 103452. https://doi.org/10.1016/j.tust.2020.103452
- I.-Y. Kim, D.-K. Cho, H.-J. Choi, Analysis on Characteristics of Reference SNF for KRS+ Design - I. PLUS7 SNF, Korea Atomic Energy Research Institute, 2019. KAERI/TR-7996/2019.
- D.-K. Cho, N.-Y. Ko, Y.-K. Koh, J.-S. Kwon, I.-Y. Kim, J.-W. Kim, J.-H. Ryu, K.W. Park, C.-K. Park, T.-J. Park, M.-H. Baik, S. Yoon, M. Lee, S.Y. Lee, J.-K. Lee, J.O. Lee, J. Lee, C. Lee, S. Jung, J. Jeong, S.-H. Ji, A Safety Case of the Conceptual Disposal System for Pyro-Processing High-Level Waste Based on the KURT Site (AKRS-16): VI. Models and Data, Korea Atomic Energy Research Institute, 2016. KAERI/TR-6732/2016.