References
- U.S. Nuclear Regulatory Commission, Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater than Class C Waste, Rules and Regulations, Title 10, Part 72, Washington DC, 2010.
- U.S. Nuclear Regulatory Commission, Packaging and Transportation of Radioactive Material, Rules and Regulations, Title 10, Part 71, Washington DC, 2009.
- IAEA Safety Standard, Regulations for the safe transport of radioactive material, in: Specific Safety Requirements No. SSR-6, IAEA, Vienna, 2012, 2012.
- U.S. Nuclear Regulatory Commission, Cladding considerations for the transportation and storage of spent fuel, Interim Staff Guidance-11 Rev. 3 (2003).
- K.J. Geelhood, C.E. Beyer, W.G. Luscher, PNNL Stress/strain Correlation for Zircaloy (PNNL-17700), Pacific Northwest National Laboratory (PNNL), 2008.
- H. Adkins, K. Geelhood, B. Koeppel, J. Coleman, J. Bignell, G. Flores, J.A. Wang, S. Sanborn, R. Spears, N. Klymyshyn, Used Fuel Disposition Campaign, Used Nuclear Fuel Loading and Structural Performance under Normal Conditions of Transport - Demonstration of Approach and Results on Used Fuel Performance Characterization (FCRD-UFD-2013-000325), U.S. Department of Energy, 2013.
- J.S. Cheon, B.H. Lee, Y.H. Koo, J.Y. Oh, D.S. Sohn, Evaluation of a pellet-clad mechanical interaction in mixed oxide fuels during power transients by using axisymmetric finite element modeling, Nucl. Eng. Des. 231 (2004) 39-50. https://doi.org/10.1016/j.nucengdes.2004.02.009
- N. Marchal, C. Campos, C. Garnier, Finite element simulation of Pellet-Cladding Interaction (PCI) in nuclear fuel rods, Comput. Mater. Sci. 45 (2009) 821-826. https://doi.org/10.1016/j.commatsci.2008.10.015
- J. Klouzal, M. Dostal, Modelling of the impact of local effects on fuel-cladding interaction during power ramp, in: 22nd International Conference on Nuclear Engineering, Prague, Czech, July 7-11, 2014.
- H.C. Kim, S.K. Seo, S.U. Lee, Y.S. Yang, Development of NUFORM3D module with FRAPCON3. 4 for simulation of pellet-cladding mechanical interaction, Nucl. Eng. Des. 318 (2017) 61-71. https://doi.org/10.1016/j.nucengdes.2017.03.035
- H. Jiang, J.A. Wang, H. Wang, The impact of interface bonding efficiency on high-burnup spent nuclear fuel dynamic performance, Nucl. Eng. Des. 309 (2016) 40-52. https://doi.org/10.1016/j.nucengdes.2016.09.013
- J.A. Wang, H. Wang, H. Jiang, B. Bevard, High burn-up spent nuclear fuel transport reliability investigation, Nucl. Eng. Des. 330 (2018) 497-515. https://doi.org/10.1016/j.nucengdes.2018.02.007
- B. Almomani, D. Jang, S. Lee, Structural integrity of a high-burnup spent fuel rod under drop impact considering pellet-clad interfacial bonding influence, Nucl. Eng. Des. 337 (2018) 324-340. https://doi.org/10.1016/j.nucengdes.2018.07.024
- R. Chun, M. Witte, M. Schwartz, Dynamic Impact Effects on Spent Fuel Assemblies (UCID-21246), Lawrence Livermore National Laboratory, 1987.
- T.L. Sanders, K.D. Seager, Y.R. Rashid, P.R. Barrett, A.P. Malinauskas, R.E. Einziger, H. Jordan, T.A. Duffey, S.H. Sutherland, P.C. Reardon, A Method for Determining the Spent-Fuel Contribution to Transport Cask Containment Requirements (SAND90-2406), Sandia National Labs, 1992.
- U.S. Nuclear Regulatory Commission, Spent Fuel Transportation Risk Assessment (NUREG-2125), Washington DC, 2014.
- R.J. Kalan, C.J.R. Clutz, D.J. Ammerman, Analysis of a 17x17 Pressurized Water Reactor (PWR) Fuel Assembly, Letter Report to the, U.S. Department of Energy, August 2005.
- G.S. Bjorkman, The buckling of fuel rods under inertia loading, Packag. Transp. Storage Secur. Radioact. Mater. 21 (2010) 165-168. https://doi.org/10.1179/174650910X12802398378394
- V. Ballheimer, F. Wille, B. Droste, Mechanical safety analysis for high burn-up spent fuel assemblies under accident transport conditions, Packag. Transp. Storage Secur. Radioact. Mater. 21 (2010) 212-217. https://doi.org/10.1179/174650910X12913756439836
- R. James, J. Rashid, R. Dunham, L. Zhang, Spent Fuel Transportation Applications:Fuel Rod Failure Evaluation under Simulated Cask Side Drop Conditions, June 2005. EPRI Technical Report 1009929.
- Electric Power Research Institute, Spent Fuel Transportation Applications:Global Forces Acting on Spent Fuel Rods and Deformation Patterns Resulting from Transportation Accidents (EPRI 1011817), EPRI, Palo Alto, CA, 2005.
- Electric Power Research Institute, Spent Fuel Transportation Applications - Assessment of Cladding Performance: A Synthesis Report (EPRI 1015048), EPRI, Palo Alto, CA, 2007.
- E. Siegmann, P. Macheret, Evaluating cladding creep during dry storage and repository emplacement, MRS Proceedings 713 (2002), https://doi.org/10.1557/PROC-713-JJ14.6.JJ14.6.
- O. Ozer, et al., Fuel-assembly Behavior under Dynamic Impact Loads Due to Dry-Storage Cask Mishandling (NP-7419), Electric Power Research Institute (EPRI), 1991.
- U.S. Nuclear Regulatory Commission, A Pilot Probabilistic Risk Assessment of a Dry Cask Storage System at a Nuclear Power Plant (NUREG-1864), 2007.
- A. Velden, P. Koch, Isight design optimization methodologies, in: D.U. Furrer, S.L. Semiatin (Eds.), ASM Handbook, Volume 22B, Metals Process Simulation, ASM International, 2010.
Cited by
- Development of Equivalent Beam Model of High Burnup Spent Nuclear Fuel Rods under Lateral Impact Loading vol.10, pp.4, 2019, https://doi.org/10.3390/met10040470
- Simulation of dynamic characteristics of NHR200-II fuel assembly vol.379, 2021, https://doi.org/10.1016/j.nucengdes.2021.111255
- Simplified Model of a High Burnup Spent Nuclear Fuel Rod under Lateral Impact Considering a Stress-Based Failure Criterion vol.11, pp.10, 2019, https://doi.org/10.3390/met11101631