Acknowledgement
The project was supported by the National Natural Science Foundation of China (51878507).
References
- 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
- 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
- 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
- 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).
- U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, Standard Review Plan for Spent Fuel Dry Storage Facilities, NUREG-1567, 2000.
- 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.
- 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.
- Korea Mest, Regulations for Packaging and Transport of Radioactive Material, Korea Mest Act, 2008, 2008-69.
- National Nuclear Safety Administration of China, Safety Regulations for Nuclear Power Plant Design, vols. 102-2016, HAF, 2016.
- 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
- 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
- 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
- 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
- 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
- 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
- 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
- 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
- MARC, Theory and User Information, 2010.
- ANSYS Structural Analysis Guide, Release 14, ANSYS INC., Southpointe, 275 Technology Drive, Canonsburg, PA 15317, USA, 2011.
- 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
- Dassault Systemes, ABAQUS 6.14 Documentation, Simulia Co., Providence, RI, USA, 2015.
- 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
- Livermore software technology corporation, LS-DYNA Keyword User's Manual Version 971, 2007.
- 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.
- 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
- 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
- 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
- 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
- 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
- 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
- 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
- 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
- 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.
- 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.
- 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.
- 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
- 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
- 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
- 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
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