최소 단어 이상 선택하여야 합니다.
최대 10 단어까지만 선택 가능합니다.
다음과 같은 기능을 한번의 로그인으로 사용 할 수 있습니다.
NTIS 바로가기Nuclear engineering and technology : an international journal of the Korean Nuclear Society, v.55 no.4, 2023년, pp.1540 - 1554
Jongyoul Lee (Korea Atomic Energy Research Institute) , Kwangil Kim (Korea Atomic Energy Research Institute) , Inyoung Kim (Korea Atomic Energy Research Institute) , Heejae Ju (Korea Atomic Energy Research Institute) , Jongtae Jeong (Korea Atomic Energy Research Institute) , Changsoo Lee (Korea Atomic Energy Research Institute) , Jung-Woo Kim (Korea Atomic Energy Research Institute) , Dongkeun Cho (Korea Atomic Energy Research Institute)
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-...
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.?
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.?
Heejae Ju, et al., Safety assessment on long-term radiological impact of the improved KAERI reference disposal system, JNFCWT 18 (S) (2020) 75-87.?
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.?
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.?
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.?
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.?
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.?
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.?
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.?
J. Rutqvist, The geomechanics of CO2 storage in deep sedimentary formations, Geotechnical Geol. Eng. 30 (3) (2012) 525-551.?
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.?
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.
*원문 PDF 파일 및 링크정보가 존재하지 않을 경우 KISTI DDS 시스템에서 제공하는 원문복사서비스를 사용할 수 있습니다.
오픈액세스 학술지에 출판된 논문
※ AI-Helper는 부적절한 답변을 할 수 있습니다.