Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Data analysis of simulated fuel-loaded sea transportation tests under normal conditions of transport

  • JaeHoon Lim (Radwaste Transportation and Storage Research Team, Korea Atomic Energy Research Institute) ;
  • Woo-seok Choi (Radwaste Transportation and Storage Research Team, Korea Atomic Energy Research Institute)
  • Received : 2023.02.15
  • Accepted : 2023.10.04
  • Published : 2024.02.25
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Abstract

In this study, to evaluate the shock and vibration load characteristics of used fuel, a sea transportation test was conducted using simulated fuel assemblies under normal transport conditions. An overall test data analysis was performed based on the measured strain and acceleration data obtained from cruise, rotation, acceleration, braking, depth of water, and rolling tests. In addition, shock response spectrum and power spectral densities were obtained for each test case. Amplification and attenuation characteristics were investigated based on the load path. The load was amplified as it passed from the overpack to the simulated used fuel-assembly. As a result of the RMS trend analysis, the fuel-loading position of the transportation package affected the measured strain in the fuel rod, and the maximum strains were obtained at the spans with large spacing. However, even these maximum strains were very small compared to the fatigue strength and the cladding yield strength. Moreover, the fuel rods located on the side exhibited a larger strain value than those at the center.

Keywords

Acknowledgement

This work was supported by the Korea Institute of Energy Technology Evaluation and Planning (KETEP) and the Ministry of Trade, Industry & Energy (MOTIE) of the Republic of Korea (No. 20211710200020) and this work was also supported by the Institute for Korea Used fuel (iKused fuel) and National Research Foundation of Korea(NRF) grant funded by the Korea government(Ministry of Science and ICT, MSIT) (No. 2021M2E1A1085229).

References

  1. C.E. Magnuson, Shock and Vibration Environments for a Large Shipping Container during Truck Transport (Part II), Sandia National Laboratories Report, NUREG/CR0128, 1978. SAND78-0337.
  2. T.L. Sanders, K.D. Seager, Y.R. Rashid, P.R. Barrett, A.P. Malinauskas, R. E. Einziger, H. Jordan, T.A. Duffey, S.H. Sutherland, P.C. Reardon, A Method for Determining the Spent-Fuel Contribution to Transport Cask Containment Requirements, Sandia National Labs., Albuquerque, NM (United States), 1992. SAND90-2406.
  3. J.H. Lim, S.S. Cho, W.S. Choi, International Research status on used fuel structural integrity tests considering shock and vibration loads under normal conditions of transport, J. Nucl. Fuel Cycle Waste Technol. 17 (2) (2019) 167-181, https://doi.org/10.7733/jnfcwt.2019.17.2.167.
  4. P. McConnell, Fuel-Assembly Shaker Test Plan-Tests for Determining Loads on Used Nuclear Fuel under Normal Conditions of Transport, 2012. FCRD-UFD-2012-000341.
  5. P. McConnell, G. Flores, R. Wauneka, G. Koenig, D. Ammerman, J. Bignell, S. Saltzstein, K. Sorenson, Fuel-assembly Shaker Test for Determining Loads on a PWR Assembly under Simulated Normal Conditions of Truck Transport, 2013. SAND2013-5210P, Rev. 0.1, FCRD-UFD-2013-000190.
  6. P. McConnell, R. Wauneka, S. Saltzstein, K. Sorenson, Normal Conditions of Transport Truck Test of a Simulated Fuel-Assembly, No. SAND2014-20495, Sandia National Laboratories (SNL-NM), 2014. FCRD-UFD-2014-000066.
  7. P. McConnell, G. Koenig, W.L. Uncapher, C. Grey, C. Engelhardt, S. Saltzstein, K. Sorenson, Simulated Fuel-Assembly Multi-Axis Shaker Tests to Simulate Normal Conditions of Rail and Truck Transport, Sandia National Lab (SNL-NM), 2016. FCRD-UFRD-2015-00128.
  8. H. Adkins, K. Geelhood, B. Koeppel, J. Coleman, J. Bignell, G. Flores, J.A. Wang, S. Sanborn, R. Spears, N.A. Klymyshyn, Used Nuclear Fuel Loading and Structural Performance under Normal Conditions of Transport-Demonstration of Approach and Results on Used Fuel Performance, in: USDOE Office of Nuclear Energy (NE), 2013. FCRD-UFD-2013-000325.
  9. N. Klymyshyn, Normal Transport Loads on Casks and Fuel-Assemblies, EPRI ESCP Meeting, Charlotte, USA, 2014. December 2.
  10. S.B. Ross, R.E. Best, N.A. Klymyshyn, P.J. Jensen, S.J. Maheras, Used Fuel Rail Shock and Vibration Testing Options Analysis, Pacific Northwest National Lab (PNNL), Richland, WA (United States), 2014. FCRD-UFD-2014-000327.
  11. P. McConnell, S. Ross, ENSA ENUN 32P rail-cask transport tests start june 2017, Spent Fuel Waste Sci. Technol. (May 24, 2017).
  12. E.A. Kalinina, C. Wright, L. Lujan, N. Gordon, S.J. Saltzstein, K.M. Norman, Data Analysis of ENSA/DOE Rail Cask Tests, Sandia National Laboratories, SFWDSFWST-2018-000494, 2018.
  13. J.H. Lim, W.S. Choi, Data analysis of international joint road and sea transportation tests under normal conditions of transport, J. Nucl. Fuel Cycle Waste Technol. 18 (2) (2020) 275-289, https://doi.org/10.7733/jnfcwt.2020.18.2(E).275.
  14. N.A. Klymyshyn, P. Ivanusa, K. Kadooka, C. Spitz, P.J. Jensen, S.B. Ross, B. D. Hanson, D. Garcia, J. Smith, S. Lewis, Modeling and Analysis of the ENSA/DOE Multimodal Transportation Campaign, Pacific Northwest National Laboratory, Richland, WA, 2018. PNNL-28088.
  15. E.A. Kalinina, D. Ammerman, C. Grey, M. Arviso, C. Wright, L. Lujan, G. Flores, S. Saltzstein, 30 Cm Drop Tests, Sandia National Laboratories, 2019. SAND2019-15256R.
  16. N. A. Klymyshyn, K. Kadooka, P. Ivanusa, C. Spitz, J. F. Fitzpatrick, 30 Cm Drop Modeling, Pacific Northwest National Lab (PNNL), PNNL-30495.
  17. J.H. Lim, W.S. Choi, Preliminary Data Analysis of Simulated Fuel-Loaded Road Transportation Tests under Normal Conditions of Transport, 54, 2022, pp. 4030-4048, https://doi.org/10.1016/j.net.2022.06.023, 11.