1 S. Stroes-Gascoyne, "The Relationship Between Gap Inventories of Stable Xenon, 137Cs, and 129I in Used CANDU Fuel" 77 (77): 320-330, 1987
2 H. Kleykamp, "The Chemical State of the Fission Products in Oxide Fuels" 131 (131): 221-246, 1985
3 F. Garisto, "Technetium-99: Review of Properties Relevant to a Canadian Geological Repository" Ontario Power Generation 2002
4 P. Lovera, "Synthesis Report on the Relevant Diffusion Coefficients of Fission Products and Helium in Spent Nuclear Fuels" Commissariat à l’énergie atomique 2003
5 L. Johnson, "Spent Fuel Radionuclide Source-term Model for Assessing Spent Fuel Performance in Geological Disposal. Part I: Assessment of the Instant Release Fraction" 346 (346): 56-65, 2005
6 L.O. Werme, "Spent Fuel Performance Under Repository Conditions: A Model for Use in SR-Can" Svensk Kärnbränslehantering AB 2004
7 M. Gobien, "Sixth Case Study: Reference Data and Codes" Nuclear Waste Management Organization 2016
8 Posiva Oy, "Safety Case for the Disposal of Spent Nuclear Fuel at Olkiluoto-Models and Data for the Repository System 2012" Posiva Oy 2013
9 C.N. Wilson, "Results From NNWSI Series 2 Bare Fuel Dissolution Tests" Pacific Northwest Laboratory 1990
10 L.H. Johnson, "Release of Segregated Nuclides From Spent Fuel" Svensk Kärnbränslehantering AB 1997
1 S. Stroes-Gascoyne, "The Relationship Between Gap Inventories of Stable Xenon, 137Cs, and 129I in Used CANDU Fuel" 77 (77): 320-330, 1987
2 H. Kleykamp, "The Chemical State of the Fission Products in Oxide Fuels" 131 (131): 221-246, 1985
3 F. Garisto, "Technetium-99: Review of Properties Relevant to a Canadian Geological Repository" Ontario Power Generation 2002
4 P. Lovera, "Synthesis Report on the Relevant Diffusion Coefficients of Fission Products and Helium in Spent Nuclear Fuels" Commissariat à l’énergie atomique 2003
5 L. Johnson, "Spent Fuel Radionuclide Source-term Model for Assessing Spent Fuel Performance in Geological Disposal. Part I: Assessment of the Instant Release Fraction" 346 (346): 56-65, 2005
6 L.O. Werme, "Spent Fuel Performance Under Repository Conditions: A Model for Use in SR-Can" Svensk Kärnbränslehantering AB 2004
7 M. Gobien, "Sixth Case Study: Reference Data and Codes" Nuclear Waste Management Organization 2016
8 Posiva Oy, "Safety Case for the Disposal of Spent Nuclear Fuel at Olkiluoto-Models and Data for the Repository System 2012" Posiva Oy 2013
9 C.N. Wilson, "Results From NNWSI Series 2 Bare Fuel Dissolution Tests" Pacific Northwest Laboratory 1990
10 L.H. Johnson, "Release of Segregated Nuclides From Spent Fuel" Svensk Kärnbränslehantering AB 1997
11 S. Stroes-Gascoyne, "Release of 14C From the Gap and Grain-Boundary Regions of Used CANDU Fuels to Aqueous Solutions" 14 (14): 385-392, 1994
12 G. Vesterlund, "Recent ABB Fuel Design and Performance Experience" ANS 62-70, 1994
13 L. Johnson, "Rapid Aqueous Release of Fission Products From High Burn-up LWR Fuel: Experimental Results and Correlations With Fission gas Release" 420 (420): 54-62, 2012
14 이종열 ; 김인영 ; 주희재 ; 최희주 ; 조동건, "Proposal of an Improved Concept Design for the Deep Geological Disposal System of Spent Nuclear Fuel in Korea" 한국방사성폐기물학회 18 : 1-19, 2020
15 J.L. Cormenzana, "Probabilistic Sensitivity Analysis for the ‘Initial Defect in the Canister’ Reference Model" 2013
16 Nuclear Waste Management Organization, "Postclosure Safety Assessment of a Used Fuel Repository in Crystalline Rock" NWMO 2017
17 Y.H. Koo, "Pore Pressure and Swelling in the Rim Region of LWR High Burnup UO2 Fuel" 295 (295): 213-220, 2001
18 L.H. Johnson, "Partitioning of Radionuclides in Swiss Power Reactor Fuels" National Cooperative for the Disposal of Radioactive Waste 2002
19 K. Lassmann, "Modelling the High Burnup UO2 Structure in LWR Fuel" 226 (226): 1-8, 1995
20 S. Stroes-Gascoyne, "Measurements of Instant-Release Source Terms for 137Cs, 90Sr, 99Tc, 129I and 14C in Used CANDU Fuels" 238 (238): 264-277, 1996
21 Svensk Kärnbränslehantering AB, "Long-term Safety for the Final Repository for Spent Nuclear Fuel at Forsmark" SKB 2011
22 W. J. Gray, "Inventories of Iodine-129 and Cesium-137in the Gaps and Grain Boundaries of LWR Spent Fuels" 556 : 487-494, 1999
23 D. Serrano-Purroy, "Instant Release Fraction and Matrix Release of High Burn-up UO2Spent Nuclear Fuel: Effect of High Burn-up Structure and Leaching Solution Composition" 427 (427): 249-258, 2012
24 E. Nordström, "Fission Gas Release Data for Ringhals PWRs" Svensk Kärnbränslehantering AB 2009
25 L. Johnson, "Estimates of the Instant Release Fraction for UO2 and MOX Fuel at t=0" National Cooperative for the Disposal of Radioactive Waste 2004
26 J.C. Tait, "Determination of Cl Impurities and 36Cl Instant Release From Used CANDU Fuels" MRS 465 : 503-510, 1997
27 Svensk Kärnbränslehantering AB, "Data Report for the Safety Assessment SR-Site" SKB 2010
28 Y.H. Koo, "Conservative Width of High-Burnup Structure in Light Water Reactor UO2 Fuel as a Function of Pellet Average Burnup" 164 (164): 337-347, 2008
29 Y.M. Lee, "A GoldSim Model for the Safety Assessment of an HLW Repository" 51 (51): 746-759, 2009