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A Systematic Approach for Mechanical Integrity Evaluation on the Degraded Cladding Tube of Spent Nuclear Fuel Under Transportation Pinch Force

  • Received : 2021.07.13
  • Accepted : 2021.08.09
  • Published : 2021.09.30

Abstract

This study developed an analytical methodology for the mechanical integrity of spent nuclear fuel (SNF) cladding tubes under external pinch loads during transportation, with reference to the failure mode specified in the relevant guidelines. Special consideration was given to the degraded characteristics of SNF during dry storage, including oxide and hydride contents and orientations. The developed framework reflected a composite cladding model of elastic and plastic analysis approaches and correlation equations related to the mechanical parameters. The established models were employed for modeling the finite elements by coding their physical behaviors. A mechanical integrity evaluation of 14 × 14 PWR SNF was performed using this system. To ensure that the damage criteria met the applicable legal requirements, stress-strain analysis results were separated into elastic and plastic regions with the concept of strain energy, considering both normal and hypothetical accident conditions. Probabilistic procedures using Monte Carlo simulations and reliability evaluations were included. The evaluation results showed no probability of damage under the normal conditions, whereas there were small but considerably low probabilities under accident conditions. These results indicate that the proposed approach is a reliable predictor of SNF mechanical integrity.

Keywords

Acknowledgement

This work was supported by the Korea Institute of Energy Technology Evaluation and Planning (KETEP) grant funded by the Korea government (MOTIE) (20181710201770, Development of Evaluation Technology for Vibration and Shock Load Characteristics and PWR Spent Nuclear Fuel Integrity under Normal Conditions of Road and Sea Transport).

References

  1. International Atomic Energy Agency. Storage of Spent Nuclear Fuel, IAEA Report, Safety Standard Series No. SSG-15 (2012).
  2. United States Nuclear Regulatory Commission. Packing and Transportation of Radioactive Material, US NRC Report, 10 CFR Part 71 (2010).
  3. United States Nuclear Regulatory Commission. Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-related Greater Than Class C Waste, US NRC Report, 10 CFR Part 72 (2020).
  4. A. Strasser, R. Adamson, and F. Garzarolli. The Effect of Hydrogen on Zirconium Alloy Properties, ANT International Report, Volume I (2008).
  5. International Atomic Energy Agency. Selection of Away-From-Reactor Facilities for Spent Fuel Storage, IAEA Technical Report, IAEA-TECDOC-1558 (2007).
  6. T.L. Sanders, K.D. Seager, Y.R. Rashid, P.R. Barrett, A.P. Malinauskas, R.E. Eingziger, H. Jordan, T.A. Duffey, S.H. Sutherland, and P.C. Reardon. A Method for Determining the Spent-Fuel Contribution to Transport Cask Containment Requirements, US Sandia National Laboraty Technical Report, SAND90-2406 (1992).
  7. A. Machiels. Dry Storage of High-Burnup Spent Fuel: Responses to Nuclear Regulatory Commission Requests for Additional Information and Clarification, Electric Power Research Institute Technical Report, 1009276 (2003).
  8. D.K. Lee et al, Composite Materials, Hongreung Science Publishing, Seoul (2007).
  9. J. Rashid, M. Rashid, and R. Dunham. Failure Criteria for Zircaloy Cladding Using a Damage-based Metal/Hydride Mixture Model, Electric Power Research Institute Technical Report, 1009693 (2004).
  10. J. Rashid, R. Dunham, M. Rashid, and A. Machiels, "A New Material Constitutive Model for Predicting Cladding Failure", Proc. of the Water Reactor Fuel Performance Meeting - WRFP/Top Fuel 2009, 127-129, September 6-10, 2009, Paris.
  11. J. Rashid, B. Dunham, Y. Zhang, and R. Montgomery. Spent Fuel Transportation Application: Longitudinal Tearing Resulting From Transportation Accidents - A Probabilistic Treatment, Electric Power Research Institute Technical Report, 1013448 (2006).
  12. O.C. Zienkiewicz, S. Valliappan, and I.P. King, "Elasto-plastic Solutions of Engineering Problems 'Initial Stress', Finite Element Approach", International Journal for Numerical Methods on Engineering, 1(1), 75-100 (1969). https://doi.org/10.1002/nme.1620010107
  13. O.C.Zienkiewicz and R.L.Taylor, The Finite Element Method-Volume 2: Solid Mechanics, 5th ed., Hutter-worth-Heinemann, Oxford (2000).
  14. Y. Yoo, K. Kim, K. Eom, and S. Lee, "Finite Element Analysis of the Mechanical Behavior of a Nuclear Fuel Assembly Spacer Grid", Nucl. Eng. Des., 352, 110179 (2019). https://doi.org/10.1016/j.nucengdes.2019.110179
  15. C. Patterson and F. Garzarolli. Dry Storage Handbook-Fuel Performance in Dry Storage, ANT Internationl, Sweden (2015).
  16. L.J. Siefken, E.W. Coryell, E.A. Harvego, and J.K. Hohorst. SCDAP/RELAP5/MOD3.3 Code Manual: MATPRO- A Library of Materials Properties for Light-Water-Reactor Accident Analysis, US Nuclear Regulatory Commission Report, NUREG/CR-6150, Vol. 4, Rev. 2 (2001).
  17. J. Rashid and A. Machiels, "Hydride Precipitation in Spent Fuel Cladding During Storage", The 10th International Conference on Environmental Remediation and Radioactive Waste Management, September 4-8, 2005, Glasgow.
  18. K.C. Kapur and L.R. Lamberson, Reliability in Engineering Design, John Wiley & Son, New York (1977).
  19. J. Rashid, F. Wong, and R. Dunham. Spent Fuel Transportaion Application: Normal Conditions of Transport, Electric Power Research Institute Technical Report, 1015049 (2007).