과제정보
This work was supported by the Ministry of Science and ICT, Republic of Korea, within the framework of the national long-term nuclear R&D program (NRF-2021M2E3A2041312).
참고문헌
- J. Lee, I. Kim, H. Ju, H. Choi, and D. Cho, "Proposal of an Improved Concept Design of the Deep Geological Disposal System of Spent Nuclear Fuel in Korea", J. Nucl. Fuel Cycle Waste Technol., 18(S), 1-19 (2020).
- L. Johnson, I. Gunther-Leopold, J.K. Waldis, H.P. Linder, J. Low, D. Cui, E. Ekeroth, K. Spahiu, and L. Z. Evins, "Rapid Aqueous Release of Fission Products From High Burn-up LWR Fuel: Experimental Results and Correlations With Fission gas Release", J. Nucl. Mater., 420(1-3), 54-62 (2012). https://doi.org/10.1016/j.jnucmat.2011.09.007
- Svensk Karnbranslehantering AB. Long-term Safety for the Final Repository for Spent Nuclear Fuel at Forsmark, SKB Technical Report, TR-11-01 (2011).
- W.J. Gray, "Inventories of Iodine-129 and Cesium-137 in the Gaps and Grain Boundaries of LWR Spent Fuels", Materials Research Society Symp. Proc., vol.556, 487-494, MRS, PA (1999).
- Y.M. Lee and Y. Hwang, "A GoldSim Model for the Safety Assessment of an HLW Repository", Prog. Nucl. Energy, 51(6-7), 746-759 (2009). https://doi.org/10.1016/j.pnucene.2009.05.002
- Posiva Oy. Safety Case for the Disposal of Spent Nuclear Fuel at Olkiluoto-Models and Data for the Repository System 2012, Posiva Oy Report, POSIVA 2013-01 (2013).
- Nuclear Waste Management Organization. Postclosure Safety Assessment of a Used Fuel Repository in Crystalline Rock, NWMO Report, NWMO-TR-2017-02 (2017).
- K. Lassmann, C.T. Walker, J. van der Laar, and F. Lindstrom, "Modelling the High Burnup UO2 Structure in LWR Fuel", J. Nucl. Mater., 226(1-2), 1-8 (1995). https://doi.org/10.1016/0022-3115(95)00116-6
- Y.H. Koo, B.H. Lee, J.Y. Oh, and K.W. Song, "Conservative Width of High-Burnup Structure in Light Water Reactor UO2 Fuel as a Function of Pellet Average Burnup", Nucl. Technol., 164(3), 337-347 (2008). https://doi.org/10.13182/NT08-A4031
- L. Johnson, C. Ferry, C. Poinssot, and P. Lovera, "Spent Fuel Radionuclide Source-term Model for Assessing Spent Fuel Performance in Geological Disposal. Part I: Assessment of the Instant Release Fraction", J. Nucl. Mater., 346(1), 56-65 (2005). https://doi.org/10.1016/j.jnucmat.2005.04.071
- S. Stroes-Gascoyne, L.H. Johnson, and D.M. Sellinger, "The Relationship Between Gap Inventories of Stable Xenon, 137Cs, and 129I in Used CANDU Fuel", Nucl. Technol., 77(3), 320-330 (1987). https://doi.org/10.13182/NT87-A33972
- L.H. Johnson and D.F. McGinnes. Partitioning of Radionuclides in Swiss Power Reactor Fuels, National Cooperative for the Disposal of Radioactive Waste Technical Report, NAGRA NTB 02-07 (2002).
- Y.H. Koo, B.H. Lee, J.S. Cheon, D.S. Sohn, "Pore Pressure and Swelling in the Rim Region of LWR High Burnup UO2 Fuel", J. Nucl. Mater., 295(2-3), 213-220 (2001). https://doi.org/10.1016/S0022-3115(01)00535-9
- L. Johnson, C. Poinssot, C. Ferry, and P. Lovera. Estimates of the Instant Release Fraction for UO2 and MOX Fuel at t=0, National Cooperative for the Disposal of Radioactive Waste Technical Report, NAGRA NTB 04-08 (2004).
- D. Serrano-Purroy, F. Clarens, E. Gonzalez-Robles, J.P. Glatz, D.H. Wegen, J. de Pablo, I. Casas, J. Gimenez, and A. Martinez-Esparza, "Instant Release Fraction and Matrix Release of High Burn-up UO2 Spent Nuclear Fuel: Effect of High Burn-up Structure and Leaching Solution Composition", J. Nucl. Mater., 427(1-3), 249-258 (2012). https://doi.org/10.1016/j.jnucmat.2012.04.036
- M. Gobien, F. Garisto, E. Kremer, and C. Medri. Sixth Case Study: Reference Data and Codes, Nuclear Waste Management Organization Report, NWMO-TR-2016-10 (2016).
- S. Stroes-Gascoyne, "Measurements of Instant-Release Source Terms for 137Cs, 90Sr, 99Tc, 129I and 14C in Used CANDU Fuels", J. Nucl. Mater., 238(2-3), 264-277 (1996). https://doi.org/10.1016/S0022-3115(96)00440-0
- S. Stroes-Gascoyne, J.C. Tait, R.J. Porth, J.L. McConnell, and W.J. Lincoln, "Release of 14C From the Gap and Grain-Boundary Regions of Used CANDU Fuels to Aqueous Solutions", Waste Manage., 14(5), 385-392 (1994). https://doi.org/10.1016/0956-053X(94)90043-4
- Svensk Karnbranslehantering AB. Data Report for the Safety Assessment SR-Site, SKB Technical Report, TR-10-52 (2010).
- J.C. Tait, R.J.J. Cornett, L.A. Chant, J. Jirovec, J. Mc-Connell, and D.L. Wilkin, "Determination of Cl Impurities and 36Cl Instant Release From Used CANDU Fuels", Materials Research Society Symp. Proc., vol.465, 503-510, MRS, Massachusetts (1997).
- H. Kleykamp, "The Chemical State of the Fission Products in Oxide Fuels", J. Nucl. Mater., 131(2-3), 221-246 (1985). https://doi.org/10.1016/0022-3115(85)90460-X
- F. Garisto and P. Gierszewski. Technetium-99: Review of Properties Relevant to a Canadian Geological Repository, Ontario Power Generation Report, 06819-REP-01200-10081-R00 (2002).
- E. Nordstrom. Fission Gas Release Data for Ringhals PWRs, Svensk Karnbranslehantering AB Technical Report, TR-09-26 (2009).
- L.O. Werme, L.H. Johnson, V.M. Oversby, F. King, K. Spahiu, B. Grambow, and D. W. Shoesmith. Spent Fuel Performance Under Repository Conditions: A Model for Use in SR-Can, Svensk Karnbranslehantering AB Technical Report, TR-04-19 (2004).
- C.N. Wilson. Results From NNWSI Series 2 Bare Fuel Dissolution Tests, Pacific Northwest Laboratory Report, PNL-7169 (1990).
- L.H. Johnson and J.C. Tait. Release of Segregated Nuclides From Spent Fuel, Svensk Karnbranslehantering AB. Technical Report, TR-97-18 (1997).
- J.L. Cormenzana. Probabilistic Sensitivity Analysis for the 'Initial Defect in the Canister' Reference Model, Posiva Working Report, 2013-25 (2013).
- P. Lovera, C. Ferry, C. Poinssot, and L. Johnson. Synthesis Report on the Relevant Diffusion Coefficients of Fission Products and Helium in Spent Nuclear Fuels, Commissariat a l'energie atomique Report, CEAR-6039 (2003).
- G. Vesterlund and L.V. Corsetti, "Recent ABB Fuel Design and Performance Experience", Proc. of the 1994 International Topical Meeting on Light Water Reactor Fuel Performance, 62-70, ANS, Florida (1994).