DOI QR코드

DOI QR Code

High-efficiency deep geological repository system for spent nuclear fuel in Korea with optimized decay heat in a disposal canister and increased thermal limit of bentonite

  • Received : 2022.09.16
  • Accepted : 2023.02.22
  • Published : 2023.04.25

Abstract

To use nuclear energy sustainably, spent nuclear fuel, classified as high-level radioactive waste and inevitably discharged after electricity generation by nuclear power plants, must be managed safely and isolated from the human environment. In Korea, the land area is limited and the amount of high-level radioactive waste, including spent nuclear fuels to be disposed, is relatively large. Thus, it is particularly necessary to maximize disposal efficiency. In this study, a high-efficiency deep geological repository concept was developed to enhance disposal efficiency. To this end, design strategies and requirements for a high-efficiency deep geological repository system were established, and engineered barrier modules with a disposal canister for pressurized water reactor (PWR)-type and pressurized heavy water reactor type Canada deuterium uranium (CANDU) plants were developed. Thermal and structural stability assessments were conducted for the repository system; it was confirmed that the system was suitable for the established strategies and requirements. In addition, the results of the nuclear safety assessment showed that the radiological safety of the new system met the Korean safety standards for disposal of high-level radioactive waste in terms of radiological dose. To evaluate disposal efficiency in terms of the disposal area, the layout of the developed disposal areas was assessed in terms of thermal limits. The estimated disposal areas were 2.51 km2 and 1.82 km2 (existing repository system: 4.57 km2) and the excavated host rock volumes were 2.7 Mm3 and 2.0 Mm3 (existing repository system: 4.5 Mm3) for thermal limits of 100 ℃ and 130 ℃, respectively. These results indicated that the area and the excavated volume of the new repository system were reduced by 40-60% compared to the existing repository system. In addition, methods to further improve the efficiency were derived for the disposal area for deep geological disposal of spent nuclear fuel. The results of this study are expected to be useful in establishing a national high-level radioactive waste management policy, and for the design of a commercial deep geological repository system for spent nuclear fuels.

Keywords

Acknowledgement

This work was supported by the Ministry of Science and ICT (MSIT) in Korea within the framework of the National Longterm Nuclear R&D Program (NRF-2017M2A8A5014856), the Institute for Korea Spent Nuclear Fuel (iKSNF), and the National Research Foundation of Korea (NRF) grant funded by MSIT (NRF-2021M2E1A1085185).

References

  1. Nuclear Safety and Security Commission, Nuclear Safety Act, 2020. 
  2. IAEA, Scientific and Technical Basis for the Geological Disposal of Radioactive Wastes, 2003. Technical Reports Series No. 413. 
  3. JNC, H12: project to establish the scientific and technical basis for HLW disposal in Japan, Second Prog. Rep. Res. Dev. Geol. Disposal HLW Jpn. Supporting Rep. 2: Repository Des. Eng. Technol. (2000). JNC TN1410. 
  4. Ministry of Trade, Industry and Energy (MOTIE), The National Basic Plan for HLW Management, MOTIE, 2016.
  5. J.Y. Lee, D.K. Cho, H.J. Choi, J.W. Choi, L.M. Wang, Analyses of disposal efficiency based on nuclear spent fuel cooling time and disposal tunnel/pit spacing for the design of a geological repository, Prog. Nucl. Energy 53 (2011) p361-p367. 
  6. J. Lee, D. Cho, H. Choi, J. Choi, Concept of a Korean reference disposal system for spent fuel, J. Nucl. Sci. Technol. 44 (12) (2007) 1565-1573.  https://doi.org/10.1080/18811248.2007.9711407
  7. A.B. Svensk Karnbranslehantering, Design Premises for a KBS-3V, Repository Based on Results from the Safety Assessment SR-Can and Some Subsequent Analyses, 2009. SKB Technical Report TR-09-22. 
  8. A.B.(S.K.B.) Svensk Karnbranslehantering, Long-term Safety for KBS-3 Repositories at Forsmark and Laxemar - a First Evaluation, 2006. TR-06-09. 
  9. In-Young Kim, Dong-Keun Cho, Analysis on Effect of Decreased Decay Time on Thermal Dimensioning of SNF Direct Disposal System, Transactions of the Korean Nuclear Society Spring Meeting Jeju, Korea, May 23-24, 2019. 
  10. J.Y. Lee, I.Y. Kim, H.J. Ju, D.K. Cho, Proposal of an Improved Concept Design for the Deep Geological Disposal System of Spent Nuclear Fuel in Korea, JNFCWT V.18 No. S, 2020. 
  11. J.W. Kim, et al., 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
  12. Heejae Ju, et al., Safety assessment on long-term radiological impact of the improved KAERI reference disposal system, JNFCWT 18 (S) (2020) 75-87.  https://doi.org/10.7733/jnfcwt.2020.18.S.75
  13. Dong-Keun Cho, Jeongwoo Kim, In-Young Kim, Jong-Youl Lee, Investigation of PWR spent fuels for the design of a deep geological repository, JNFCWT 17 (3) (2019) 339-346.  https://doi.org/10.7733/jnfcwt.2019.17.3.339
  14. J.Y. Lee, D.K. Cho, H.J. Choi, J.W. Choi, L.M. Wang, Efficiency analyses of the CANDU spent fuel repository using modified disposal canisters for a deep geological disposal system design, Nucl. Eng. Des. 242 (2012) 433-444.  https://doi.org/10.1016/j.nucengdes.2011.10.039
  15. D.K. Cho, S.K. Yoon, H.J. Choi, J.W. Choi, W.I. Ko, Reference spent nuclear fuel for pyro-processing facility design, J. Korean Radioact. Waste Soc. 6 (2008). 
  16. D.K. Cho, D.H. Kook, H.J. Choi, J.W. Choi, Development of a simplified source term estimation model for a spent fuel from Westinghouse-type Reactors, J. Kor. Radioact. Waste Soc. 8 (3) (2010) 239-245. 
  17. G. Gaus, K. Wieczorek, EBS Performance at Temperature above 100℃ - PEBS Case 3, Proc. of. Int. Conf. on the Performance of Engineered Barriers, Hannover, 2014. 
  18. Ernest Hardin, Teklu Hadgu, Dan Clayton, Repository reference disposal concepts and thermal load management analysis, FCRD-UFD-2012-00219 Rev. 2 (2012) 20-33. 
  19. NUMO, Development of Repository Concepts for Volunteer Siting Environments, NUMO Technical Report No. NUMO-TR-04-03, 2004. 
  20. M. Juvankoski, K. Ikonen, T. Jalonen, Buffer Production Line 2012-Design, Production and Initial State of the Buffer, POSIVA Oy Report, 2012. POSIVA 2012-17. 
  21. A.B.(S.K.B. Svensk Karnbranslehantering, Buffer and Backfill Process Report for the Safety Assessment SR-Can, SKB Technical Report, 2006. SKB-TR-06-18. 
  22. C.S. Lee, W.J. Cho, J.S. Kim, H.J. Choi, Characterization of Thermal and Mechanical Properties of Granite at KAERI Underground Research Tunnel, Korea Atomic Energy Research Institute, 2014, pp. 20-29. KAERI/TR-5566/2014. 
  23. J.W. Kim, et al., A Safety Case of the Conceptual Disposal System for Pyro-Processing High-Level Wastes Based on the KURT Site (AKRS-16): VII. Post-Closure Safety Assessment, Korea Atomic Energy Research Institute, 2016. KAERI/TR-6733/2016. 
  24. Radioactive Waste Management (RWM), Geological Disposal Overview of the Generic Disposal System Safety Case, Nuclear Decommissioning Authority Report, 2016. NDA Report no. DSSC/101/01. 
  25. The Atomic Energy Promotion Commission (AEPC), The 2nd National Basic Plan for HLW Management, MOTIE, 2021. 
  26. NAGRA, Demonstration of Disposal Feasibility for Spent Fuel, Vitrified High Level Waste and Long Lived Intermediate-Level Waste (Entsorgungsnachweis), NAGRA Technical Report 02-05, National Cooperative for the Disposal of Radioactive Waste, 2002. 
  27. Heikki, Design Analysis Report for the Canister, Svensk Karnbranslehantering AB Technical Report, 2010, pp. 5-16. SKB-TR-10-28. 
  28. NSSC (Nuclear Safety and Security Commission), General criteria on deep geological disposal facility for high level radioactive waste, NSSC Notice 2021 77 (2021). 
  29. J.Y. Lee, et al., An improved concept of deep geological disposal system considering arising characteristics of spent fuels from domestic nuclear power plants, J. Nucl. Fuel Cycle Waste Technol. 17 (4) (2019) 405-418.  https://doi.org/10.7733/jnfcwt.2019.17.4.405
  30. J.T. Jeong, J.W. Kim, D.K. Cho, Development of a Combination Method of a Decay Heat of a Canister for the Performance Improvement of a Repository, Korea Atomic Energy Research Institute, 2020, pp. 35-49. KAERI/TR-5566/2014. 
  31. Jongtae Jeong, et al., Optimization of spent nuclear fuels per canister to improve the disposal efficiency of a deep geological repository in Korea, Nucl. Eng. Technol. 54 (2022) 2819-2827.  https://doi.org/10.1016/j.net.2022.02.017
  32. D.K. Cho, D.H. Kook, H.J. Choi, J.W. Choi, Development of a simplified source term estimation model for a spent fuel from Westinghouse-type Reactors, J. Korean Radioactive Waste Soc. 8 (3) (2010) 239-245. 
  33. K. Zhang, Y.S. Wu, K. Pruess, User's Guide for TOUGH2-MP - A Massively Parallel Version of the TOUGH2 Code, Lawrence Berkeley National Laboratory Report LBNL-315E, Berkeley, CA, USA, 2008. 
  34. Jae Owan Lee, Minsoo Lee, Heuijoo Choi, Establishing the concept of buffer for a high-level radioactive waste repository: an approach, JNFCWT 13 (4) (2015) 283-293. 
  35. 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, Tunneling Underground Space Technol. 103 (2020), 103452. 
  36. K.I. Kim, C. Lee, J.S. Kim, 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) (2021) 221-242.  https://doi.org/10.7474/TUS.2021.31.4.221
  37. J. Rutqvist, Y.S. Wu, C.F. Tsang, G. Bodvarsson, A modeling approach for analysis of coupled multiphase fluid flow, heat transfer, and deformation in fractured porous rock, Int. J. Rock Mechanics Mining Sci. 39 (4) (2002) 429-442.  https://doi.org/10.1016/S1365-1609(02)00022-9
  38. J. Rutqvist, Status of the TOUGH-FLAC simulator and recent applications related to coupled fluid flow and crustal deformations, Comput. Geosciences 37 (6) (2011) 739-750.  https://doi.org/10.1016/j.cageo.2010.08.006
  39. J. Rutqvist, The geomechanics of CO2 storage in deep sedimentary formations, Geotechnical Geol. Eng. 30 (3) (2012) 525-551.  https://doi.org/10.1007/s10706-011-9491-0
  40. C. Lee, J. Lee, G.Y. Kim, Numerical analysis of coupled hydro-mechanical and thermo-hydro-mechanical behavior in buffer materials at a geological repository for nuclear waste: simulation of EB experiment at Mont Terri URL and FEBEX at Grimsel test site using Barcelona basic model, Int. J. Rock Mechanics Mining Sci. 139 (2021), 104663. 
  41. J.H. Synn, C. Park, B.J. Lee, Regional distribution pattern and geo-historical transition of in-situ stress fields in the Korean Peninsula, Tunneling and Underground Space 23 (6) (2013) 457-469.  https://doi.org/10.7474/TUS.2013.23.6.457
  42. J.C. Jaeger, G.W. N, Fundamentals of Rock Mechanics, 1979. London. 
  43. Z.T. Bieniawski, The rock mass rating (RMR) system (geomechanics classification) in engineering practice, in rock classification systems for engineering purposes, ASTM Int. 17-34 (1988). 
  44. H. Raiko, Disposal Canister for Spent Nuclear Fuel- Design Report, POSIVA Oy Report2005-02, 2005. 
  45. 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, JNFCWT 18 (S) (2020). 
  46. Dassault Systems, Abaqus/CAE User's Manual, Dassault systems simulia Corp., 2019. 
  47. Nuclear Waste Management Organization of Japan (NUMO), The NUMO Presiting SDM-based Safety Case, 2021. NUMO-TR-21-01.