과제정보
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).
참고문헌
- Nuclear Safety and Security Commission, Nuclear Safety Act, 2020.
- IAEA, Scientific and Technical Basis for the Geological Disposal of Radioactive Wastes, 2003. Technical Reports Series No. 413.
- 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.
- Ministry of Trade, Industry and Energy (MOTIE), The National Basic Plan for HLW Management, MOTIE, 2016.
- 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.
- 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
- 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.
- 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.
- 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.
- 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.
- 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
- 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
- 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
- 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
- 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).
- 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.
- 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.
- Ernest Hardin, Teklu Hadgu, Dan Clayton, Repository reference disposal concepts and thermal load management analysis, FCRD-UFD-2012-00219 Rev. 2 (2012) 20-33.
- NUMO, Development of Repository Concepts for Volunteer Siting Environments, NUMO Technical Report No. NUMO-TR-04-03, 2004.
- 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.
- 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.
- 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.
- 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.
- 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.
- The Atomic Energy Promotion Commission (AEPC), The 2nd National Basic Plan for HLW Management, MOTIE, 2021.
- 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.
- Heikki, Design Analysis Report for the Canister, Svensk Karnbranslehantering AB Technical Report, 2010, pp. 5-16. SKB-TR-10-28.
- NSSC (Nuclear Safety and Security Commission), General criteria on deep geological disposal facility for high level radioactive waste, NSSC Notice 2021 77 (2021).
- 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
- 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.
- 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
- 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.
- 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.
- 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.
- 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.
- 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
- 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
- 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
- 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
- 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.
- 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
- J.C. Jaeger, G.W. N, Fundamentals of Rock Mechanics, 1979. London.
- 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).
- H. Raiko, Disposal Canister for Spent Nuclear Fuel- Design Report, POSIVA Oy Report2005-02, 2005.
- 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).
- Dassault Systems, Abaqus/CAE User's Manual, Dassault systems simulia Corp., 2019.
- Nuclear Waste Management Organization of Japan (NUMO), The NUMO Presiting SDM-based Safety Case, 2021. NUMO-TR-21-01.