DOI QR코드

DOI QR Code

Development of a Probabilistic Safety Assessment Framework for an Interim Dry Storage Facility Subjected to an Aircraft Crash Using Best-Estimate Structural Analysis

  • Almomani, Belal (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) ;
  • Jang, Dongchan (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) ;
  • Lee, Sanghoon (Department of Mechanical and Automotive Engineering, Keimyung University) ;
  • Kang, Hyun Gook (Department of Mechanical, Aerospace and Nuclear Engineering, Rensselaer Polytechnic Institute)
  • Received : 2016.12.07
  • Accepted : 2016.12.27
  • Published : 2017.04.25

Abstract

Using a probabilistic safety assessment, a risk evaluation framework for an aircraft crash into an interim spent fuel storage facility is presented. Damage evaluation of a detailed generic cask model in a simplified building structure under an aircraft impact is discussed through a numerical structural analysis and an analytical fragility assessment. Sequences of the impact scenario are shown in a developed event tree, with uncertainties considered in the impact analysis and failure probabilities calculated. To evaluate the influence of parameters relevant to design safety, risks are estimated for three specification levels of cask and storage facility structures. The proposed assessment procedure includes the determination of the loading parameters, reference impact scenario, structural response analyses of facility walls, cask containment, and fuel assemblies, and a radiological consequence analysis with dose-risk estimation. The risk results for the proposed scenario in this study are expected to be small relative to those of design basis accidents for best-estimated conservative values. The importance of this framework is seen in its flexibility to evaluate the capability of the facility to withstand an aircraft impact and in its ability to anticipate potential realistic risks; the framework also provides insight into epistemic uncertainty in the available data and into the sensitivity of the design parameters for future research.

Keywords

References

  1. U.S. Nuclear Regulatory Commission, A pilot probabilistic risk assessment of a dry cask storage system at a nuclear power plant, NUREG-1864, 2007.
  2. NUS Corporation, Review of proposed dry-storage concepts using probabilistic risk assessment, EPRI NP-3365, 1984.
  3. 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
  4. 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
  5. 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
  6. 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.
  7. 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.
  8. 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
  9. 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
  10. 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.
  11. U.S. Department of Energy, Accident analysis for aircraft crash into hazardous facilities, DOE-STD-3014, 2006.
  12. 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
  13. 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.
  14. 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.
  15. 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
  16. Nuclear Energy Institute, Methodology for performing aircraft impact assessments for new plant designs, NEI 07-13, Revision 8P, 2011.
  17. E. Kausel, Speed of Aircraft, Ch. 3 [Internet]. 2002. Available from: http://web.mit.edu/civenv/wtc/. [Accessed April 2016].
  18. 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).
  19. 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.
  20. Livermore Software Technology Corporation, LS-DYNA Keyword User's Manual, Version 971, 2007. California.
  21. 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].
  22. Sandia National Laboratory, Reexamination of spent fuel shipment risk estimates, NUREG/CR-6672, 2004.
  23. 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.
  24. 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.
  25. US Nuclear Regulatory Commission, Spent fuel transportation risk assessment, NUREG-2125, 2012.
  26. 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
  27. S.G. Homann, HotSpot-Health Physics Codes-Version 2.071-User's Guide, National Atmospheric Release Advisory Center, Lawrence Livermore National Laboratory, 2010.

Cited by

  1. Failure probability assessment of SNF cladding transverse tearing under a hypothetical transportation accident vol.379, pp.None, 2021, https://doi.org/10.1016/j.nucengdes.2021.111265