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A Study on Thermal Load Management in a Deep Geological Repository for Efficient Disposal of High Level Radioactive Waste

  • Received : 2022.07.07
  • Accepted : 2022.09.21
  • Published : 2022.12.30

Abstract

Technology for high-level-waste disposal employing a multibarrier concept using engineered and natural barrier in stable bedrock at 300-1,000 m depth is being commercialized as a safe, long-term isolation method for high-level waste, including spent nuclear fuel. Managing heat generated from waste is important for improving disposal efficiency; thus, research on efficient heat management is required. In this study, thermal management methods to maximize disposal efficiency in terms of the disposal area required were developed. They efficiently use the land in an environment, such as Korea, where the land area is small and the amount of waste is large. The thermal effects of engineered barriers and natural barriers in a high-level waste disposal repository were analyzed. The research status of thermal management for the main bedrocks of the repository, such as crystalline, clay, salt, and other rocks, were reviewed. Based on a characteristics analysis of various heat management approaches, the spent nuclear fuel cooling time, buffer bentonite thermal conductivity, and disposal container size were chosen as efficient heat management methods applicable in Korea. For each method, thermal analyses of the disposal repository were performed. Based on the results, the disposal efficiency was evaluated preliminarily. Necessary future research is suggested.

Keywords

Acknowledgement

This work was supported by the Ministry of Science and ICT within the framework of the national long-term nuclear R&D program (NRF-2021M23A2041312).

References

  1. International Atomic Energy Agency, Effects of Heat From High-level Waste on Performance of Deep Geological Repository Components, 14-26, IAEA-TECDOC-319 (1984).
  2. T.W. Hicks, M.J. White, and P.J. Hooker. Role of Bentonite in Determination of Thermal Limits on Geological Disposal Facility Design, Galson Sciences Ltd. Report, 12-26, Report 0883-1, version 2 (2009).
  3. J.S. Kim, W.J. Cho, S. Park, G.Y. Kim, and M.H. Baik, "A Review on the Design Requirement of Temperature in High-level Nuclear Waste Disposal System: Based on Bentonite Buffer", J. Korean Tunn. Undergr. Sp. Assoc., 21(5), 587-609 (2019). https://doi.org/10.9711/KTAJ.2019.21.5.587
  4. S. Vomvoris, J. Birkholzer, L. Zheng, I. Gaus, and I. Blechschmidt, "THMC Behavior of Clay-based Barriers Under High Temperature - From Laboratory to URL Scale", Proc. of 15th International High-Level Radioactive Waste Management Conference, 678-687, Charleston, NC, USA (2015).
  5. K. Ikonen. Thermal Analyses of Spent Nuclear Fuel Repository, Posiva Oy Report, Posiva 2003-04 (2003).
  6. A. Lempinen. THM Model Parameters for Compacted Bentonite, Posiva Oy Working Report, 2006-79 (2006).
  7. H. Harald and B. Faelth. Thermal Dimensioning of the Deep Repository. Influence of Canister Spacing, Canister Power, Rock Thermal Properties and Nearfield Design on the Maximum Canister Surface Temperature, Svensk Karnbranslehantering AB Technical Report, SKB-TR-03-09 (2003).
  8. R. Christiansson, Design of the Radioactive Waste Repository in Sweden Swedish Nuclear and Fuel Waste Management Co. (2011).
  9. K. Rasilainen. Localisation of the SR 97 Process Report for Posiva's Spent Fuel Repository at Olkiluoto, Posiva Technical Report, Posiva 04-05 (2004).
  10. P. Smith, L. Johnson, M. Snellman, B. Pastina, and P. Gribi. Safety Assessment for a KBS-3H Spent Nuclear Fuel Repository at Olkiluoto Evolution Report, Posiva Report, POSIVA 2007-8 (2007).
  11. L. Ahonen, P. Korkeakoski, M. Tiljander, H. Kivikoski, and R. Laaksonen. Quality Assurance of the Bentonite Material, Posiva Oy Working Report, 2008-33 (2008).
  12. J. Palomaki and L. Ristimaki. Facility Description 2012 Summary Report of the Encapsulation Plant and Disposal Facility Designs, Posiva Oy Working Report, 2012-66 (2013).
  13. Agence nationale pour la gestation des dechets radioactifs. Dossier 2005 Argile SYNTHESIS Evaluation of the Feasibility of a Geological Repository in an Argillaceous Formation, Andra Report Series (2005).
  14. Agence nationale pour la gestation des dechets radioactifs. Dossier 2005 Andra Research on the Geological Disposal of High-level Long-lived Radioactive Waste. Results and Perspective, Andra Report (2005).
  15. National Cooperative for the Disposal of Radioactive Waste. Demonstration of Disposal Feasibility for Spent Fuel, Vitrified High-level Waste and Long-lived Intermediate-level Waste (Entsorgungsnachweis), Nagra Technical Report, 02-05 (2002).
  16. O.X. Leupin, P. Smith, P. Marschall, L. Johnson, D. Savage, V. Cloet, J. Schneider, and R. Senger. High level Waste Repository induced Effects, Nagra Technical Report, 14-13 (2016).
  17. I. Blechschmidt, Radioactive Waste Management in Switzerland Short Update, KAERI-NAGRA Technical Meeting, 9-16, Daejeon (2017).
  18. W. Bollingerfehr, W. Filbert, and J. Wehrmann, "Emplacement Technology for the Direct Disposal of Spent Fuel Into Deep Vertical Boreholes", International Conference Underground Disposal Unit Design & Emplacement Processes for a Deep Geological Repository, June 16-18, 2008, Prague.
  19. R. Graf and W. Filbert, "Disposal of Spent Fuel From German Nuclear Power Plants - Paper Work or Technology", Presentation at the Topseal Conference, September 17-20, 2006, Finland.
  20. Sandia National Laboratories, Total System Performance Assessment Data Input Package for Requirements Analysis for DOE SNF/HLW and Navy SNF Waste Package Overpack Physical Attributes Basis for Performance Assessment, TDR-TDIF_ES-000009 REC.00, Las Vagas, Nevada (2007).
  21. U.S. Department of Energy Office of Civilian Radioactive Waste Management. Yucca Mountain Science and Engineering Report, U.S. Department of Energy Report, DOE/RW-0539-1 (2002).
  22. Posiva Oy. Interim Summary Report of the Safety Case 2009, Posiva Oy Report, 10-02 (2010).
  23. Svensk Karnbranslehantering AB. Long-term Safety for KBS-3 Repositories at Forsmark and Laxemar - a First Evaluation, SKB Technical Report, TR-06-09 (2006).
  24. Agence nationale pour la gestation des dechets radioactifs. Dossier 2005 Argile - Architecture and Management of a Geological Disposal System, Andra Report (2005).
  25. L.H. Johnson and F. King. Canister Options for the Disposal of Spent Fuel, Nagra Technical Report , NTB 02-11 (2003).
  26. H.N. Kalia, "Simulated Waste Package Test in Salt", International High Level Radioactive Waste Management Conference, May 22-26, 1994, Las Vegas.
  27. U.S. Department of Energy. Site Characterization Plan Conceptual Design Report for a High-Level Nuclear Waste Repository in Salt, Horizontal Emplacement Mode: Volume 1, U.S. Department of Energy Report, DOE/CH-46656-14(1) (1987).
  28. U.S. Department of Energy. Yucca Mountain Repository License Application for Construction Authorization, U.S. Department of Energy Report, DOE/RW-0573, Rev.0, Section 1.3.1.2.5 (2008).
  29. Nuclear Safety & Security Commission, General Standards for Deep Geological Disposal Facility of High-level Radioactive Wastes, Public Notice of NSSC 2017-74 (2017).
  30. Japan Nuclear Cycle Development Institute. H12: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan. Second Progress Report on Research and Development for the Geological Disposal of HLW in Japan, Supporting Report 2: Repository Design and Engineering Technology, JNC Report, JNC TN1410 2000-003 (2000).
  31. H.J. Choi and J. Choi, "Double-layered Buffer to Enhance the Thermal Performance in a High-level Radioactive Waste Disposal System", Nucl. Eng. Des., 238(10), 2815-2820 (2008). https://doi.org/10.1016/j.nucengdes.2008.04.017
  32. ONDRAF/NIRAS. Technical Overview of the SAFIR 2 Report, Safety Assessment and Feasibility Interim Report 2, ONDRAF/NIRAS Report, NIROND 2001-05 E (2001).
  33. P. Wersin, L.H. Johnson, and I.G. McKinley, "Performance of the Bentonite Barrier at Temperatures Beyond 100℃: A Critical Review", Phys. Chem. Earth, 32(8-14), 780-788 (2007). https://doi.org/10.1016/j.pce.2006.02.051
  34. H. Kawamura, I.G. McKinley, and F.B. Neall, "Practical and Safe Implementation of Disposal With Prefabricated EBS Modules", Proc. of International Technical Conference on Practical Aspects of Deep Radioactive Waste Disposal Session 2, No. 8, June 16-18, 2008, Prague.
  35. S. Masuda, H. Kawamura, I. McKinley, F. Neall, and H. Umeki, "Optimising Repository Design for the CARE Concept", 11th International High-Level Radioactive Waste Management Conference, 507-514, Las Vegas, USA (2006).
  36. L. Zheng, J. Rutqvist, J.T. Birkholzer, and H.H. Liu, "On the Impact of Temperatures up to 200℃ in Clay Repositories With Bentonite Engineer Barrier Systems: A Study With Coupled Thermal, Hydrological, Chemical, and Mechanical Modeling", Eng. Geol., 197, 278-295 (2015). https://doi.org/10.1016/j.enggeo.2015.08.026
  37. T.W. Hicks and M.B. Crawford. Co-disposal of HLW and Spent Fuel With ILW and LLW Viability Study: Hydro-Thermo-Mechanical Effects, Galson Sciences Ltd. Report, 9902-1 (2002).
  38. Nuclear Waste Management Organization of Japan. Development of Repository Concepts for Volunteer Siting Environments, NUMO Technical Report, NUMO-TR-04-03 (2004).
  39. I.G. McKinley, F.B. Neall, P.A. Smith, J.M. West, and H. Kawamura, "Evolution of the Cavern-Extended Storage (CES) Concept for Flexible Management of HLW", MRS Online Proceedings Library, 807, 695-700 (2003). https://doi.org/10.1557/PROC-807-695
  40. S. Masuda, H. Umeki, I. McKinley, and H. Kawamura, "Management With CARE", Nucl. Eng. Int., 49(604), 26-29 (2004).
  41. D.K. Cho, J.W. Kim, I.Y. Kim, and J.Y. Lee, "Investigation of PWR Spent Fuels for the Design of a Deep Geological Repository", J. Nucl. Fuel Cycle Waste Technol., 17(3), 339-346 (2019). https://doi.org/10.7733/jnfcwt.2019.17.3.339
  42. I.Y. Kim, H.A. Kim, and H.J. Choi. Evaluation on Thermal Performance and Thermal Dimensioning of Direct Deep Geological Disposal System for High Burn-up Spent Nuclear Fuel, Korea Atomic Energy Research Institute Technical Report, KAERI/TR-5230/2013 (2013).
  43. Svensk Karnbranslehantering AB, Final Storage of Spent Fuel - KBS-3, Stockholm (1983).
  44. H.J. Choi, J.Y. Lee, and D.K. Cho. Korean Reference HLW Disposal System, Korea Atomic Energy Research Institute Technical Report, KAERI/TR-3563 (2008).
  45. Y.A. Cengel, A.J. Ghajar, and M. Kanoglu, Heat and Mass Transfer: Fundamentals and Applications, 4th ed., McGraw-Hill, New York (2011).