Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

Structural integrity of KJRR-F fresh nuclear fuel under vehicle-induced vibration for normal transport condition

  • Jeong, Gil-Eon (Radwaste Transportation and Storage Research Team, Korea Atomic Energy Research Institute) ;
  • Yang, Yun-Young (Radwaste Transportation and Storage Research Team, Korea Atomic Energy Research Institute) ;
  • Bang, Kyoung-Sik (Radwaste Transportation and Storage Research Team, Korea Atomic Energy Research Institute)
  • Received : 2021.06.27
  • Accepted : 2021.09.30
  • Published : 2022.04.25
Download PDF
⟨ Previous Next ⟩

Abstract

Nuclear fuel, including its fresh state, must be handled safely due to its critical and hazardous nature. Under normal transport conditions, several interactions take place among different components, such as transport cask used for loading the nuclear fuel and tie-down structure to attach with the vehicle. To ensure structural integrity of the nuclear fuel, vibrations and impacts transmitted from the vehicle must be sufficiently reduced. Therefore, in this study, we conducted two transportation tests from Daejeon to Kijang in Korea to verify the vehicle-induced vibrational characteristics of the KJRR-F fresh nuclear fuel when transported under normal transport conditions. The speed and location of the vehicle were obtained via GPS, and the accelerations between the vehicle and the KJRR-F fresh nuclear fuel were measured. Additionally, using the acceleration results, a structural analysis was conducted to confirm the structural integrity of the nuclear fuel under the most severe conditions during normal transport.

Keywords

Acknowledgement

This work was supported by the Ministry of Science and ICT (MSIT) of the Republic of Korea. (No. 2020M2C1A1061066). And this work was partially supported by the Institute for Korea Spent Nuclear Fuel (iKSNF) and National Research Foundation of Korea (NRF) grant funded by the Korean government (Ministry of Science and ICT, MSIT) (No. 2021M2E1A1085229).

References

  1. G.E. Jeong, W.S. Choi, S.S. Cho, Topology optimization of tie-down structure for transportation of metal cask containing spent nuclear fuel, Nucl. Eng. Technol. 53 (2021) 2268-2276, https://doi.org/10.1016/j.net.2021.01.019.
  2. M. Yun, et al., A software tool for integrated risk assessment of spent fuel transportation and storage, Nucl. Eng. Technol. 49 (2017) 721-733, https://doi.org/10.1016/j.net.2017.01.017.
  3. L. Tao, et al., Probabilistic safety assessment method for spent nuclear fuel road transportation, Ann. Nucl. Energy 137 (2020) 107043, https://doi.org/10.1016/j.anucene.2019.107043.
  4. J. Jeong, D.K. Cho, H.J. Choi, J.W. Choi, Comparison of the transportation risks for the spent fuel in Korea for different transportation scenarios, Ann. Nucl. Energy 38 (2011) 535-539, https://doi.org/10.1016/j.anucene.2010.09.030.
  5. H. Jiang, J.J. Wang, Spent nuclear fuel system dynamic stability under normal conditions of transportation, Nucl. Eng. Des. 310 (2016) 1-14, https://doi.org/10.1016/j.nucengdes.2016.09.033.
  6. W.S. Choi, J.H. Lim, J.M. Lim, Y.Y. Yang, G.E. Jeong, S.S. Cho, Current status of Korean multi-modal transportation test (MMTT), in: Transactions of the Korean Nuclear Society Virtual Spring Meeting, 2020.
  7. B. Almomani, D. Jang, S. Lee, Structural integrity of a high-burnup spent fuel rod under drop impact considering pellet-clad interfacial bonding influence, Nucl. Eng. Des. 337 (2018) 324-340, https://doi.org/10.1016/j.nucengdes.2018.07.024.
  8. L. Tao, L. Chen, P. Long, C. Chen, J. Wang, Integrated risk assessment method for spent fuel road transportation accident under complex environment, Nucl. Eng. Technol. 53 (2021) 393-398, https://doi.org/10.1016/j.net.2020.09.030.
  9. B. Almomani, S. Kim, D. Jang, S. Lee, Parametric study on the structural response of a high burnup spent nuclear fuel rod under drop impact considering post-irradiated fuel conditions, Nucl. Eng. Technol. 52 (2020) 1079-1092, https://doi.org/10.1016/j.net.2019.10.022.
  10. R.C. Ewing, Long-term storage of spent nuclear fuel, Nat. Mater. 14 (2015) 252-257, https://doi.org/10.1038/nmat4226.
  11. T. Saegusa, et al., Review and future issues on spent nuclear fuel storage, Nucl. Eng. Technol. 42 (2010) 237-248, https://doi.org/10.5516/NET.2010.42.3.237.
  12. J.H. Ko, J.H. Park, I.S. Jung, G.U. Lee, C.Y. Baeg, T.M. Kim, Shielding analysis of dual purpose casks for spent nuclear fuel under normal storage conditions, Nucl. Eng. Technol. 46 (2014) 547-556, https://doi.org/10.5516/NET.08.2013.039.
  13. A. Ryabov, V. Romanov, G. Sotskov, Numerical simulations of dynamic deformation of air transport fresh fuel package in accidental impacts, in: WM'03 Conference, 2003.
  14. M. Pesic, O. Sotic, Experiences from HEU fresh fuel transportation from Yugoslavia to Russia, in: 7th Topical Meeting on Research Reactor Fuel Management (RRFM), European Nuclear Society (ENS) in cooperation with the International Atomic Energy Agency (IAEA), 2003. https://www.osti.gov/etdeweb/servlets/purl/20399860#page=232.
  15. P. McConnell, R. Wauneka, S. Saltzstein, K. Sorenson, Normal Conditions of Transport Truck Test of a Surrogate Fuel Assembly, 2014.
  16. Kijang Research REACTOR, reportFuel Design Report.
  17. ANSYS, Workbench, 12 1.
  18. H.J. Kim, Y.W. Tahk, H. Jun, E.H. Kong, J.Y. Oh, J.S. Yim, Establishment of the design stress intensity value for the plate-type fuel assembly using a tensile test, Nucl. Eng. Technol. 53 (2021) 911-919, https://doi.org/10.1016/j.net.2020.07.038.
  19. G.E. Jeong, Y.Y. Yang, K.S. Bang, 'Normal Transportation Test Report for the KJRR-F Fresh Fuel Transport Cask' KAERI-TR-8557, 2021 [in Korean].
  20. H.J. Kim, J.S. Yim, B.H. Lee, J.Y. Oh, Y.W. Tahk, Drop imapck analysis of plate-type fuel assembly in research reactor, Nucl. Eng. Technol. 46 (2014) 529-540, https://doi.org/10.5516/NET.09.2013.103.