Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

Safety assessment of nuclear fuel reprocessing plant under the free drop impact of spent fuel cask and fuel assembly part I: Large-scale model test and finite element model validation

  • Li, Z.C. (State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment, China Nuclear Power Engineering Co., Ltd) ;
  • Yang, Y.H. (College of Civil Engineering, Tongji University) ;
  • Dong, Z.F. (State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment, China Nuclear Power Engineering Co., Ltd) ;
  • Huang, T. (State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment, China Nuclear Power Engineering Co., Ltd) ;
  • Wu, H. (College of Civil Engineering, Tongji University)
  • Received : 2020.08.10
  • Accepted : 2021.02.03
  • Published : 2021.08.25
Download PDF
⟨ Previous Next ⟩

Abstract

This paper aims to evaluate the structural dynamic responses and damage/failure of the nuclear fuel reprocessing plant under the free drop impact of spent fuel cask (SFC) and fuel assembly (FA) during the on-site transportation. At the present Part I of this paper, the large-scale SFC model free drop test and the corresponding numerical simulations are performed. Firstly, a composite target which is composed of the protective structure, i.e., a thin RC plate (representing the inverted U-shaped slab in the loading shaft) and/or an autoclaved aerated concrete (AAC) blocks sacrificial layer, as well as a thick RC plate (representing the bottom slab in the loading shaft) is designed and fabricated. Then, based on the large dropping tower, the free drop test of large-scale SFC model with the mass of 3 t is carried out from the height of 7 m-11 m. It indicates that the bottom slab in the loading shaft could not resist the free drop impact of SFC. The composite protective structure can effectively reduce the damage and vibrations of the bottom slab, and the inverted U-shaped slab could relieve the damage of the AAC blocks layer dramatically. Furthermore, based on the finite element (FE) program LS-DYNA, the corresponding refined numerical simulations are performed. By comparing the experimental and numerical damage and vibration accelerations of the composite structures, the present adopted numerical algorithms, constitutive models and parameters are validated, which will be applied in the further assessment of drop impact effects of full-scale SFC and FA on prototype nuclear fuel reprocessing plant in the next Part II of this paper.

Keywords

Acknowledgement

The project was supported by the National Natural Science Foundation of China (51878507).

References

  1. H. Othman, T. Sabrah, H. Marzouk, Conceptual design of ultra-high performance fiber reinforced concrete nuclear waste container, Nucl. Eng. Technol. 51 (2019) 588-599. https://doi.org/10.1016/j.net.2018.10.014
  2. R. Lo Frano, D. Aquaro, D. Giorla, D. Del Serra, Thermal tests of a scaled down mock-up of CP5.2 packaging system: post-test analysis, Prog. Nucl. Energy 107 (2018) 1-9. https://doi.org/10.1016/j.pnucene.2018.04.009
  3. R. Lo Frano, D. Del Serra, D. Aquaro, Thermal tests of a CP5.2 packaging system: prototype and experimental test description, Prog. Nucl. Energy 105 (2018) 247-253. https://doi.org/10.1016/j.pnucene.2018.02.004
  4. IAEA Safety Standards Series, Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material, Safety Guide, 2008. No. TS-G-1.1 (Rev. 1).
  5. U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, Standard Review Plan for Spent Fuel Dry Storage Facilities, NUREG-1567, 2000.
  6. American Society of Mechanical Engineers, ASME BPVC section III-rules for construction of nuclear facility components-division 3, in: Containments for Transportation and Storage of Spent Nuclear Fuel and High Level Radioactive Material and Waste, 2015.
  7. Nuclear and Industrial Safety Agency of the Japanese Government, Technical Requirements on Interim Spent Fuel Storage Facility Using Dry Metal Cask, 2006. NISA-314c-06-02.
  8. Korea Mest, Regulations for Packaging and Transport of Radioactive Material, Korea Mest Act, 2008, 2008-69.
  9. National Nuclear Safety Administration of China, Safety Regulations for Nuclear Power Plant Design, vols. 102-2016, HAF, 2016.
  10. T.Y. Wu, H.Y. Lee, L.C. Kang, Dynamic response analysis of a spent-fuel dry storage cask under vertical drop accident, Ann. Nucl. Energy 42 (2012) 18-29. https://doi.org/10.1016/j.anucene.2011.12.016
  11. T. Saegusa, G. Yagawa, M. Aritomi, Topics of research and development on concrete cask storage of spent nuclear fuel, Nucl. Eng. Des. 238 (2008) 1168-1174. https://doi.org/10.1016/j.nucengdes.2007.03.031
  12. G. Pugliese, R. Lo Frano, G. Forasassi, Spent fuel transport cask thermal evaluation under normal and accident conditions, Nucl. Eng. Des. 240 (2010) 1699-1706. https://doi.org/10.1016/j.nucengdes.2010.02.033
  13. A.T. Silva, M. Mattar Neto, R.P. Mourao, L.L. Silva, C.C. Lopes, M.C.C. Silva, Options for the interim storage of IEA-R1 research reactor spent fuels, Prog. Nucl. Energy 50 (2008) 836-844. https://doi.org/10.1016/j.pnucene.2007.07.004
  14. Y. Saito, J. Kishimoto, T. Matsuoka, H. Tamaki, A. Kitada, Containment integrity evaluation of MSF-type cask for interim storage and transport of PWR spent fuel, Int. J. Pres. Ves. Pip. 117-118 (2014) 33-41. https://doi.org/10.1016/j.ijpvp.2013.10.007
  15. K. Shirai, T. Saegusa, Demonstrative drop tests of transport and storage fullscale canisters with high corrosion-resistant material, Nucl. Eng. Des. 238 (2008) 1241-1249. https://doi.org/10.1016/j.nucengdes.2007.03.039
  16. R. Lo Frano, G. Pugliese, M. Nasta, Structural performance of an IP2 package in free drop test conditions: numerical and experimental evaluations, Nucl. Eng. Des. 280 (2014) 634-643. https://doi.org/10.1016/j.nucengdes.2014.09.034
  17. R. Lo Frano, A. Sanfiorenzo, Demonstration of structural performance of IP-2 package by simulation and full-scale horizontal free drop test, Prog. Nucl. Energy 86 (2016) 40-49. https://doi.org/10.1016/j.pnucene.2015.09.014
  18. MARC, Theory and User Information, 2010.
  19. ANSYS Structural Analysis Guide, Release 14, ANSYS INC., Southpointe, 275 Technology Drive, Canonsburg, PA 15317, USA, 2011.
  20. S.P. Kim, J. Kim, D. Sohn, H. Kwon, M. Shin, Stress-based vs. strain-based safety evaluations of spent nuclear fuel transport casks in energy-limited events, Nucl. Eng. Des. 355 (2019) 110324. https://doi.org/10.1016/j.nucengdes.2019.110324
  21. Dassault Systemes, ABAQUS 6.14 Documentation, Simulia Co., Providence, RI, USA, 2015.
  22. T.Y. Wu, H.Y. Lee, L.C. Kang, Dynamic response analysis of a spent-fuel dry storage cask under vertical drop accident, Ann. Nucl. Energy 42 (2012) 18-29. https://doi.org/10.1016/j.anucene.2011.12.016
  23. Livermore software technology corporation, LS-DYNA Keyword User's Manual Version 971, 2007.
  24. D. Aquaro, N. Zaccari, M. Di Prinzio, G. Forasassi, Numerical and experimental analysis of the impact of a nuclear spent fuel cask, Nucl. Eng. Des. 242 (2010) 706-712.
  25. J. Wang, H. Ren, X. Wu, C. Cai, Blast response of polymer-retrofitted masonry unit walls, Compos. B Eng. 128 (2017) 174-181. https://doi.org/10.1016/j.compositesb.2016.02.044
  26. A. Bayat, G.H. Liaghat, M. Ghalami-Choobar, G.D. Ashkezari, H. Sabouri, Analytical modeling of the high-velocity impact of autoclaved aerated concrete (AAC) blocks and some experimental results, Int. J. Mech. Sci. 159 (2019) 315-324. https://doi.org/10.1016/j.ijmecsci.2019.05.043
  27. J.C. Serrano-Perez, U.K. Vaidya, N. Uddin, Low velocity impact response of autoclaved aerated concrete/CFRP sandwich plates, Compos. Struct. 80 (2007) 621-630. https://doi.org/10.1016/j.compstruct.2006.07.013
  28. V. Dey, G. Zani, M. Colombo, M. Di Prisco, B. Mobasher, Flexural impact response of textile-reinforced aerated concrete sandwich panels, Mater. Des. 86 (2015) 187-197. https://doi.org/10.1016/j.matdes.2015.07.004
  29. B. Wang, Y. Chen, H. Fan, F. Jin, Investigation of low-velocity impact behaviors of foamed concrete material, Compos. B Eng. 162 (2019) 491-499. https://doi.org/10.1016/j.compositesb.2019.01.021
  30. E.P. Kearsley, P.J. Wainwright, Porosity and permeability of foamed concrete, Cement Concr. Res. 31 (2001) 805-812. https://doi.org/10.1016/S0008-8846(01)00490-2
  31. L.E. Schwer, Y.D. Murray, A three invariant smooth cap model with mixed hardening, Int. J. Numer. Anal. Methods GeoMech. 18 (10) (1994) 657-688. https://doi.org/10.1002/nag.1610181002
  32. S. Govindjee, G.J. Kay, J.C. Simo, Anisotropic modelling and numerical simulation of brittle damage in concrete, Int. J. Numer. Methods Eng. 38 (21) (1995) 3611-3633. https://doi.org/10.1002/nme.1620382105
  33. G.R. Johnson, W.H. Cook, A constitutive model and data for metals subjected to large strains, high strain rates and high temperatures, in: Proceedings of the 7th International Symposium on Ballistics, Hague, vol. 21, 1983, pp. 541-547.
  34. R.D. Krieg, S.W. Key, Implementation of a time dependent plasticity theory into structural computer programs, Am. Soc. Mech. Eng. Appl. Mech. Div. AMD 20 (1976) 125-137.
  35. S.T. Marais, R.B. Tait, T.J. Cloete, G.N. Nurick, Material test at high strain rate using the split Hopkinson pressure bar, Lat. Am. J. Solid. Struct. 1 (2004) 319-339.
  36. T.M. Pham, H. Hao, Effect of the plastic hinge and boundary conditions on the impact behavior of reinforced concrete beams, Int. J. Impact Eng. 102 (2017) 74-85. https://doi.org/10.1016/j.ijimpeng.2016.12.005
  37. A. Pavlovic, C. Fragassa, A. Disic, Comparative numerical and experimental study of projectile impact on reinforced concrete, Compos. B Eng. 108 (2017) 122-130. https://doi.org/10.1016/j.compositesb.2016.09.059
  38. X. Chen, F. Lu, D. Zhang, Penetration trajectory of concrete targets by ogived steel projectiles-Experiments and simulations, Int. J. Impact Eng. 120 (2018) 202-213. https://doi.org/10.1016/j.ijimpeng.2018.06.004
  39. Z. Li, L. Chen, Q. Fang, H. Hao, Y. Zhang, W. Chen, H. Xiang, Q. Bao, Study of autoclaved aerated concrete masonry walls under vented gas explosions, Eng. Struct. 141 (2017) 444-460. https://doi.org/10.1016/j.engstruct.2017.03.033

Cited by

  1. Numerical simulations of nuclear fuel reprocessing plant subjected to the free drop impact of spent fuel cask and fuel assembly vol.385, 2021, https://doi.org/10.1016/j.nucengdes.2021.111524