2104. Comparison between simulation and experimental result of the scale down vertical concrete cask under the historical earthquake hit
Che-Wei Hu1, Chi-Che Hung2, Yuan-Chieh Wu3, Wei-Ting Lin4
1Micron Memory Taiwan, Taichung 421, Taiwan
2, 3Institute of Nuclear Energy Research, Atomic Energy Council, Taoyuan 325, Taiwan
4Department of Civil Engineering, National Ilan University, Ilan 260, Taiwan
E-mail: email@example.com, firstname.lastname@example.org, email@example.com, firstname.lastname@example.org
Received 9 December 2015; received in revised form 1 June 2016; accepted 20 June 2016
Abstract. In recent years, the final disposal facility for the long-term storage of high radioactive waste is an important issue and an urgent task for nuclear Industry. This study is focus on the understanding the procedure of dry storage system in a nuclear power plant. The dry storage system is known as transportable storage canister (TSC) packing by using spent fuel placed in vertical concrete cask (VCC) or VCC with add-on-shell (AOS) canister and then those conveyed VCC or AOS will be put on the concrete pad. A numerical simulation for evaluation the behavior of VCC and AOC under the earthquake hits is used the finite element model by LS-DYNA and the real seismic behavior is obtained using shaking table test. Test results indicate that the simulation by numerical model can slightly simulate the dynamic records by shaking table test. This is because that the behavior of shaking table test is the rocking motion but the numerical model is the sliding motion. The surface roughness between the cask and concrete pad is an important variable and it needs more numerical simulation to solve the interface and friction coefficient between the cask and concrete pad.
Keywords: dry storage, LS-DYNA, numerical verification, finite element model.
 Hsu S. K., Lo C. L. Change of crustal gravitational potential energy in the Taiwan orogen by the Chi‑Chi earthquake sequence. Earth and Planetary Science Letters, Vol. 222, Issue 2, 2004, p. 573‑581.
 Liao Y. H., Lin S. F., Liao W. H., Huang J. H., Shen M., Lin C. H., Huang C. H. Deaths related to housing in 1999 Chi-Chi, Taiwan, earthquake. Safety Science, Vol. 43, Issue 1, 2005, p. 29‑37.
 Takewaki I., Fujita K., Yoshitomi S. Uncertainties in long-period ground motion and its impact on building structural design: case study of the 2011 Tohoku (Japan) earthquake. Engineering Structures, Vol. 49, 2013, p. 119‑134.
 Koseki J., Koda M., Matsuo S., Takasaki H., Fujiwara T. Damage to railway earth structures and foundations caused by the 2011 off the Pacific Coast of Tohoku earthquake. Soils and Foundations, Vol. 52, Issue 5, 2012, p. 872‑889.
 Chapman N., Hooper A. The disposal of radioactive wastes underground. Proceedings of the Geologists’ Association, Vol. 123, Issue 1, 2012, p. 46‑63.
 Yoshida H., Aoki K., Semba T., Ota K., Amano K., Hama K., Kawamura M., Tsubot K. Overview of the stability and barrier functions of the granitic geosphere at the Kamaishi Mine: relevance to radioactive waste disposal in Japan. Engineering Geology, Vol. 56, Issues 1‑2, 2000, p. 151‑162.
 Liu S. J., Soong K. L., Yang J. T. Final disposal of spent nuclear fuel in Taiwan: a state‑of‑the‑art technical overview. Waste Management, Vol. 9, Issue 3, 1989, p. 171‑188.
 Chen K. C., Ting K., Li Y. C., Chen Y. Y., Cheng W. K., Chen W. C., Liu C. T. A study of the probabilistic risk assessment to the dry storage system of spent nuclear fuel. International Journal of Pressure Vessels and Piping, Vol. 87, Issue 1, 2010, p. 17‑25.
 Lin C. Y., Wu T. Y., Huang C. C. Nonlinear dynamic impact analysis for installing a dry storage canister into a vertical concrete cask. International Journal of Pressure Vessels and Piping, Vol. 131, 2015, p. 22‑35.
 Huang C. C., Wu T. Y. A study on dynamic impact of vertical concrete cask tip-over using explicit finite element analysis procedures. Annals of Nuclear Energy, Vol. 36, Issue 2, 2009, p. 213‑221.
 Shirai K., Hirata K., Saegusa T. Experimental studies of free-standing spent fuel storage cask subjected to strong earthquakes. SMiRT 17, Prague, Czech Republic, 2003.
 Saegusa T., Shirai K., Arai T., Tani J., Takeda H., Wataru M., Sasahar A., Winston P. L. Review and future issues on spent nuclear fuel storage. Nuclear Engineering and Technology, Vol. 42, Issue 3, 2010, p. 237‑248.
 Witte M., et al. Summary and Evaluation of Low-Velocity Impact Tests of Solid Steel Billet onto Concrete Pads. NUREG/CR-6608, UCRL-ID-129211, 1998.
 Lundberg O. E., Nordborg A., Arteage I. L. The influence of surface roughness on the contact stiffness and the contact filter effect in nonlinear wheel‑track interaction. Journal of Sound and Vibration, Vol. 366, 2016, p. 429‑446.
 Wu T., Thompson D. J. Theoretical investigation of wheel‑rail non-linear interaction due to roughness excitation. Vehicle System Dynamics, International Journal of Vehicle Mechanics and Mobility, Vol. 34, Issue 4, 2000, p. 261‑282.
Cite this article
Hu Che‑Wei, Hung Chi‑Che, Wu Yuan‑Chieh, Lin Wei‑Ting Comparison between simulation and experimental result of the scale down vertical concrete cask under the historical earthquake hit. Journal of Vibroengineering, Vol. 18, Issue 5, 2016, p. 3048‑3056.
© JVE International Ltd. Journal of Vibroengineering. Aug 2016, Vol. 18, Issue 5. ISSN 1392-8716