References
- U.S. Nuclear Regulatory Commission, A pilot probabilistic risk assessment of a dry cask storage system at a nuclear power plant, NUREG-1864, 2007.
- NUS Corporation, Review of proposed dry-storage concepts using probabilistic risk assessment, EPRI NP-3365, 1984.
- S. Lee, W.-S. Choi, K.-S. Seo, Safety assessment of a metal cask under aircraft engine crash, Nucl. Eng. Technol. 48 (2016) 505-517. https://doi.org/10.1016/j.net.2015.11.002
- J.-H. Yoon, W.-S. Choi, S. Lee, K.-S. Seo, Arising technical issues in the development of a transportation and storage system of spent nuclear fuel in Korea, J. Nucl. Eng. Technol. 43 (2011) 413-420. https://doi.org/10.5516/NET.2011.43.5.413
- K. Shirai, K. Namba, T. Saegusa, Safety analysis of dual purpose metal cask subjected to impulsive load due to aircraft engine crash, J. Power Energy Syst. 3 (2009) 72-82. https://doi.org/10.1299/jpes.3.72
- B. Droste, H. Volzke, G. Wieser, L. Qiao, Safety margins of spent fuel transport and storage casks considering aircraft crash impacts, Radioact. Mater. Transp. 13 (2002) 313-316.
- G. Marchaud, L. Vilela, S. Nallet, Designing a radioactive material storage cask against airplane crashes with LS-DYNA, 3rd International LS-DYNA Users Conference, Dearborn, Michigan, USA, 2014, pp. 1-11.
- G. Wieser, L. Qiao, A. Eberle, H. Volzke, Thermo-mechanical finite element analyses of bolted cask lid, Packag. Transp. Storage Secur. Radioact. Mater. 15 (2004) 223-230. https://doi.org/10.1179/174650904775295667
- G. Wieser, L. Qiao, H. Volzke, D. Wolff, B. Droste, Safety analysis of casks under extreme impact conditions, Packag. Transp. Storage Secur. Radioact. Mater. 15 (2004) 141-147. https://doi.org/10.1179/174650904775295937
- J. Stepan, J. Maly, I. Holub, Consequences of the large commercial aircraft crash into the interim spent fuel storage facility, Proceedings of SMiRT 18, Beijing, China, 2005.
- U.S. Department of Energy, Accident analysis for aircraft crash into hazardous facilities, DOE-STD-3014, 2006.
- B. Almomani, S. Lee, D. Jang, H.G. Kang, Probabilistic risk assessment of aircraft impact on a spent nuclear fuel dry storage, Nucl. Eng. Des. 311 (2017) 104-119. https://doi.org/10.1016/j.nucengdes.2016.11.012
- B. Thomauske, Realization of German concept for interim storage of spent nuclear fuel=current situation and prospect, Proceedings of WM03, Tucson, AZ, USA, February 23-27, 2003.
- D. Wolff, M. Jaunich, U. Probst, S. Nagelschmidt, Understanding the long-term behavior of sealing systems and neutron shielding material for extended dry cask storage, Probabilistic Safety Assessment and Management PSAM 12, PSAM12, Honolulu, Hawaii, June 2014.
- B. Almomani, S. Lee, H.G. Kang, Structural analysis of a metal spent-fuel storage cask in an aircraft crash for risk assessment, Nucl. Eng. Des. 308 (2016) 60-72. https://doi.org/10.1016/j.nucengdes.2016.07.014
- Nuclear Energy Institute, Methodology for performing aircraft impact assessments for new plant designs, NEI 07-13, Revision 8P, 2011.
- E. Kausel, Speed of Aircraft, Ch. 3 [Internet]. 2002. Available from: http://web.mit.edu/civenv/wtc/. [Accessed April 2016].
- G. Kessler, A. Veser, F.-H. Schluter, W. Raskob, C. Landman, J. Pasler-Sauer, The Risk of Nuclear Energy Technology, Springer, Berlin Heidelberg, 2014. http://doi:10.1007/978-3-642-55116-1. ISBN: 978-3-642-55116-1 (eBook).
- A. Oztemel, S. Sensoy, Mathematical model for the probability distribution of in-situ concrete compressive strength in north Cyprus, in: 29th Conference on Our World in Concrete & Structures, Singapore, 2004, pp. 387-395.
- Livermore Software Technology Corporation, LS-DYNA Keyword User's Manual, Version 971, 2007. California.
- Dassault Systemes, ABAQUS Unified FEA: Complete Solutions for Realistic Simulation [Internet]. 2014. Available from: http://www.3ds.com/products-services/simulia/products/abaqus. [Accessed November 2016].
- Sandia National Laboratory, Reexamination of spent fuel shipment risk estimates, NUREG/CR-6672, 2004.
- Sandia National Laboratory, Data and methods for assessment of the risks associated with the maritime transport of radioactive materials results of the SeaRAM program studies, SAND98-1171/2, 1998.
- I.C. Gauld, S.M. Bowman, J.E. Horwedel, ORIGEN-ARP: automatic rapid processing for spent fuel depletion, decay, and source term analysis, Oak Ridge National Laboratory, Oak Ridge (TN), 2006. ORNL/TM-2005/39.
- US Nuclear Regulatory Commission, Spent fuel transportation risk assessment, NUREG-2125, 2012.
- R.E. Einziger, C. Beyer, Characteristics and behavior of high-burnup fuel that may affect the source terms for cask accidents, Nucl. Technol. 159 (2007) 134-146. https://doi.org/10.13182/NT07-A3860
- S.G. Homann, HotSpot-Health Physics Codes-Version 2.071-User's Guide, National Atmospheric Release Advisory Center, Lawrence Livermore National Laboratory, 2010.
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