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http://dx.doi.org/10.7733/jnfcwt.2020.18.S.21

Analyses on Thermal Stability and Structural Integrity of the Improved Disposal Systems for Spent Nuclear Fuels in Korea  

Lee, Jongyoul (Korea Atomic Energy Research Institute)
Kim, Hyeona (Korea Atomic Energy Research Institute)
Kim, Inyoung (Korea Atomic Energy Research Institute)
Choi, Heuijoo (Korea Atomic Energy Research Institute)
Cho, Dongkeun (Korea Atomic Energy Research Institute)
Publication Information
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT) / v.18, no.spc, 2020 , pp. 21-36 More about this Journal
Abstract
With respect to spent nuclear fuels, disposal containers and bentonite buffer blocks in deep geological disposal systems are the primary engineered barrier elements that are required to isolate radioactive toxicity for a long period of time and delay the leakage of radio nuclides such that they do not affect human and natural environments. Therefore, the thermal stability of the bentonite buffer and structural integrity of the disposal container are essential factors for maintaining the safety of a deep geological disposal system. The most important requirement in the design of such a system involves ensuring that the temperature of the buffer does not exceed 100℃ because of the decay heat emitted from high-level wastes loaded in the disposal container. In addition, the disposal containers should maintain structural integrity under loads, such as hydraulic pressure, at an underground depth of 500 m and swelling pressure of the bentonite buffer. In this study, we analyzed the thermal stability and structural integrity in a deep geological disposal environment of the improved deep geological disposal systems for domestic light-water and heavy-water reactor types of spent nuclear fuels, which were considered to be subject to direct disposal. The results of the thermal stability and structural integrity assessments indicated that the improved disposal systems for each type of spent nuclear fuel satisfied the temperature limit requirement (< 100℃) of the disposal system, and the disposal containers were observed to maintain their integrity with a safety ratio of 2.0 or higher in the environment of deep disposal.
Keywords
Spent nuclear fuel; Deep geological disposal; Design requirements; Bentonite block; Disposal container; Thermal stability; Structural integrity;
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Times Cited By KSCI : 4  (Citation Analysis)
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1 J.Y. Lee, D.K. Cho, H.J. Choi, J.W. Choi, and 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(4), 361-367 (2011).   DOI
2 Svensk Karnbranslehantering AB. Buffer and backfill process report for the safety assessment SR-Can, SKB Technical Report, 27-33, SKB-TR-06-18 (2006).
3 M. Juvankoski and K. Ikonen. Buffer Production Line 2012 - Design, Production and Initial State of the Buffer, POSIVA Oy Report, 73-74, POSIVA 2012-17 (2012).
4 R. Heikki. Design analysis report for the canister, Svensk Karnbranslehantering AB Technical Report, 5-16, SKB-TR-10-28 (2010).
5 H. Raiko. Disposal Canister for Spent Nuclear Fuel-Design Report, POSIVA Oy Report, 15-16, POSIVA 2005-02 (2005).
6 J.Y. Lee, D. Cho, H. Choi, and J. Choi, "Concept of a Korean Reference Disposal System for Spent Fuels", J. Nucl. Sci. Technol., 44(12), 1565-1573 (2007).   DOI
7 H.J. Choi, J.Y. Lee, D.K.Cho, S.K. Kim, S.S. Kim, K.Y. Kim, J.T. Jeong, M.S. Lee, J.W. Choi, J.W. Lee, K.S. Chun, and P.O. Kim. Korean Reference HLW Disposal System, Korea Atomic Energy Research Institute Technical Report, 53-73, KAERI/TR-3563/2008 (2008).
8 J.Y. Lee, I.Y. Kim, H.J. Choi, and D.K. Cho, "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), 405-418 (2019).   DOI
9 G.D. Sizgek, "Three-dimensional thermal analysis of in-floor type nuclear waste repository for a ceramic waste form", Nucl. Eng. Des., 235(1), 101-109 (2005).   DOI
10 Dassault systems, Abaqus/CAE User's manual, Dassault systems simulia Corp. (2019).
11 I.Y. Kim, H.A. Kim, 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, 3-16, KAERI/TR-5230/2013 (2013).
12 D.K. Cho, J.W. Kim, I.Y. Kim, and J.Y. Lee, "Investigation of PWR Spent Nuclear Fuels for the Design of Deep Geological Repository", J. Nucl. Fuel Cycle Waste Technol., 17(3), 339-346 (2019).   DOI
13 H. J. Choi, I.Y. Kim, and H.A. Kim. Thermal Analyses of a Geological Disposal System for High-level Waste under Abnormal Overheating Conditions, Korea Atomic Energy Research Institute Technical Report, 8-14, KAERI/TR-5635/2014 (2014).
14 Nuclear Waste Management Organization. ThermoMechanical Analysis of a Multi-Level Repository for Used Nuclear Fuel, NWMO Report, 10-25, NWMOTR-2012-19 (2012).
15 M. Smedstad. The use of nodular ductile cast iron in storage canisters for spent nuclear fuel in conjunction with ASME Section III. FSD102131201, Rev 07, FS Dynamics Sweden AB, SKBdoc 1527035 ver 1.0 (2016).
16 J.Y. Lee, M.S. Lee, I.Y. Kim, and D.K. Cho. An Engineered Barrier Concept of Reference Deep Geological Disposal System for Hi-burnup Spent Fuels, Korea Atomic Energy Research Institute Technical Report, 45-49, KAERI/TR-7405/2018 (2018).
17 Posiva and Svensk Karnbranslehantering AB, Mechanical design analysis for the canister, 41-57, Posiva SKB Report 04 (2018).
18 M. Unosson. Investigation of criteria for handling and the principal of mechanical requirements of the copper shell, SKBdoc 1492223 ver 1.0 (2017).
19 O. Martin, K.-F. Nilsson, and N. Jaksic, "Numerical simulation of plastic collapse of copper castiron iron canister for spent nuclear fuel", Eng. Fail. Anal., 16(1), 225-241 (2009).   DOI
20 Svensk Karnbranslehantering AB. Design, production and initial state of the canister, SKB Technical Report, 37-45, SKB-TR-10-14 (2010).
21 C.S. Lee, W.J. Cho, J.S. Kim, and H.J. Choi. Characterization of thermal and mechanical properties of granite at KAERI Underground research Tunnel, Korea Atomic Energy Research Institute Technical Report, 20-29, KAERI/TR-5566/2014 (2014).