1 "U.S. NRC Interim StaffGuidance-11 Rev. 3, Cladding Considerations for the Transportation and Storage of Spent Fuel"
2 "U.S. NRC 10 CFR Part 72, Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater than Class c Waste"
3 "U.S. NRC 10 CFR Part 71, Packaging and Transportation of Radioactive Material"
4 방신효 ; 김호아 ; 노재수 ; 김동욱 ; 금경환 ; 이유호, "Temperature-dependent axial mechanical properties of Zircaloy-4 with various hydrogen amounts and hydride orientations" 한국원자력학회 54 (54): 1579-1587, 2022
5 "Standard Review Plan for Dry Cask Storage Systems" U. S. Nuclear Regulatory Commission 1997
6 A. J. Machiels, "Spent Fuel Transportation Applications: Global Forces Acting on Spent Fuel Rods and Deformation Patterns Resulting from Transportation Accidents" EPRI 2005
7 R. James, "Spent Fuel Transportation Applications: Fuel Rod Failure Evaluation under Simulated Cask Side Drop Conditions" EPRI 2005
8 J. Rashid, "Spent Fuel Transportation Applications-Assessment of Cladding Performance: A Synthesis Report" EPRI 2007
9 국동학 ; 최종원 ; 김주성 ; 김용수, "Review of Spent Fuel Integrity Evaluation for Dry Storage" 한국원자력학회 45 (45): 115-124, 2013
10 IAEA Safety Standards, "Regulations for the Safe Transport of Radioactive Material" 2012
1 "U.S. NRC Interim StaffGuidance-11 Rev. 3, Cladding Considerations for the Transportation and Storage of Spent Fuel"
2 "U.S. NRC 10 CFR Part 72, Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater than Class c Waste"
3 "U.S. NRC 10 CFR Part 71, Packaging and Transportation of Radioactive Material"
4 방신효 ; 김호아 ; 노재수 ; 김동욱 ; 금경환 ; 이유호, "Temperature-dependent axial mechanical properties of Zircaloy-4 with various hydrogen amounts and hydride orientations" 한국원자력학회 54 (54): 1579-1587, 2022
5 "Standard Review Plan for Dry Cask Storage Systems" U. S. Nuclear Regulatory Commission 1997
6 A. J. Machiels, "Spent Fuel Transportation Applications: Global Forces Acting on Spent Fuel Rods and Deformation Patterns Resulting from Transportation Accidents" EPRI 2005
7 R. James, "Spent Fuel Transportation Applications: Fuel Rod Failure Evaluation under Simulated Cask Side Drop Conditions" EPRI 2005
8 J. Rashid, "Spent Fuel Transportation Applications-Assessment of Cladding Performance: A Synthesis Report" EPRI 2007
9 국동학 ; 최종원 ; 김주성 ; 김용수, "Review of Spent Fuel Integrity Evaluation for Dry Storage" 한국원자력학회 45 (45): 115-124, 2013
10 IAEA Safety Standards, "Regulations for the Safe Transport of Radioactive Material" 2012
11 K. J. Geelhood, "PNNL Stress/Strain Correlation for Zircaloy" Pacific Northwest National Laboratory (PNNL) 2008
12 A. T. Motta, "Hydrogen in zirconium alloys : a review" 518 : 440-460, 2019
13 B. Almomani, "Failure probability assessment of SNF cladding transverse tearing under a hypothetical transportation accident" 379 : 111265-, 2021
14 S. Kang, "Comparative stress analyses of dropped spent nuclear fuel assembly in a prototypal cask" ASME 2020
15 "ASTM E8/E8M-21, Standard Test Methods for Tension Testing of Metallic Materials"
16 ABAQUS, "ABAQUS User’s Manual Ver. 2020" Dassault Systemes 2020
17 E. Eidelpes, "A probabilistic assessment of PWR SNF pinching failure considering hydride-related cladding embrittlement" 351 : 116-130, 2019
18 E. Eidelpes, "A probabilistic assessment of PWR SNF cladding pinching failure considering potential transportation accident conditions" 358 : 110423-, 2020
19 T. L. Sanders, "A Method for Determining the Spent-Fuel Contribution to Transport Cask Containment Requirements" Sandia National Labs 1992
20 N. A. Klymyshyn, "30 cm Drop Modeling" Pacific Northwest National Laboratory 2020