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Mathematical modelling of nonlinear vibration and fretting wear of the nuclear fuel rods

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Abstract

The paper deals with modelling of nonlinear flexural vibration of nuclear fuel rod in hexagonal-type nuclear fuel assembly. The fuel rods are transversally linked to each other by spacer grid cells to inside the fuel assembly skeleton in several level spacings. The main components of the fuel rods are cladding in the form of thin-walled tubes of zirconium and fuel pellet columns incorporated in-tube with radial clearance. The flexural fuel rod vibration, caused by the fuel assembly support plate motion in the reactor core, can exhibit impulse contact forces between fuel rod components and possible loss of contact between the fuel rod cladding and some of spacer grid cells. Dynamic forces transmitted between fuel rods and spacer grid cells are used for calculation of expected lifetime period of nuclear fuel assembly in terms of fuel rod cladding abrasion. The presented method introduces the first known approach to mathematical modelling of fuel rod nonlinear vibration and fretting wear varying during reactor operation.

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References

  1. Arkadov, G.V., Pavelko, V.I., Usanov, A.I.: Vibrošumovaja Diagnostika VVER. Eněrgoatomizdat, Moskva (2004)

    Google Scholar 

  2. Blau, P.J.: A multi-stage wear model for grid-to-rod fretting of nuclear fuel rods. Wear 313(1–2), 89–96 (2014). doi:10.1016/j.wear.2014.02.016. http://www.sciencedirect.com/science/article/pii/S004316481400060X

  3. Hlaváč, Z., Zeman, V.: Vibration of Nuclear Fuel Assemblies: Modelling, Methods, Application. LAP Lambert Academic Publishing, Saarbrűcken (2013)

    Google Scholar 

  4. Kim, H.K., Lee, Y.H., Lee, K.H.: On the geometry of the fuel rod supports concerning a fretting wear failure . Nucl. Eng. Des. 238(12), 3321–3330 (2008). doi:10.1016/j.nucengdes.2008.08.010. http://www.sciencedirect.com/science/article/pii/S0029549308004494

  5. Kim, K.T.: A study on the grid-to-rod fretting wear-induced fuel failure observed in the 1616KOFA fuel. Nucl. Eng. Des. 240(4), 756–762 (2010). doi:10.1016/j.nucengdes.2009.12.014. http://www.sciencedirect.com/science/article/pii/S0029549309006554

  6. Kim, K.T.: The effect of fuel rod supporting conditions on fuel rod vibration characteristics and grid-to-rod fretting wear. Nucl. Eng. Des. 240(6), 1386–1391 (2010). doi:10.1016/j.nucengdes.2009.12.030. http://www.sciencedirect.com/science/article/pii/S0029549310000166

  7. Lavreňuk, P.I.: Osnovanije sovmestnosti TVSA-T, PS CUZ i SVP s projektom AES temelín. Technical Report TEM-GN-01, Sobstvennos\(\check{\rm {t}}\) OAO TVEL (2009). (In Russian)

  8. Lee, Y.H., Kim, H.K.: Effect of spring shapes on the variation of loading conditions and the wear behaviour of the nuclear fuel rod during fretting wear tests . Wear 263(16), 451–457 (2007). doi:10.1016/j.wear.2006.12.071. http://www.sciencedirect.com/science/article/pii/S0043164807004243. (16th International Conference on Wear of Materials)

  9. Lee, Y.H., Kim, H.K.: Fretting wear behavior of a nuclear fuel rod under a simulated primary coolant condition. Wear 301(1–2), 569–574 (2013). doi:10.1016/j.wear.2013.01.067. http://www.sciencedirect.com/science/article/pii/S0043164813000896. (Wear of Materials 2013)

  10. Leine, R.I., Nijmeijer, H.: Dynamics and bifurcations of non-smooth mechanical systems. In: Lecture Notes in Applied and Computational Mechanics. Springer (2004). https://books.google.cz/books?id=CYxR-61vsMYC

  11. Lu, R., Karoutas, Z., Sham, T.L.: Casl virtual reactor predictive simulation: Grid-to-rod fretting wear. JOM 63(8), 53–58 (2011). doi:10.1007/s11837-011-0139-6

    Article  Google Scholar 

  12. Makarov, V.V., et al.: Isledovanije processov trenija i iznosa konstruktivnych elementov těplovydeljajuščich sborok vodovodjanych energetičeskich reaktorov. In: 7th International and Scientific Conference Safety Assuarance of NPP with WWER. Podolsk (2011)

  13. Pečínka, L., Stulík, P.: The experimental verification of the reactor WWER 1000/320 dynamic response caused by pressure pulsations generated by main circulation pumps. In: Pešek, L. (ed.) Proceedings of Colloquium Dynamics of Machines 2008, pp. 87–94. Institute of Thermomechanics AS CR, Prague (2008)

    Google Scholar 

  14. Pečínka, L., Svoboda, J., Zeman, V.: Fretting wear of the Zr fuel rod cladding. In: Proceedings of the 2014 22nd International Conference of Nuclear Engineering ICONE22 (2014, In press)

  15. Rubiolo, P.R.: Probabilistic prediction of fretting-wear damage of nuclear fuel rods. Nucl. Eng. Des. 236(1416), 1628–1640 (2006). doi:10.1016/j.nucengdes.2006.04.023. http://www.sciencedirect.com/science/article/pii/S0029549306003451. (13th International Conference on Nuclear Energy 13th International Conference on Nuclear Energy)

  16. Smolík, J.: VVANTAGE6 fuel assembly mechanical test. Technical Report No. Ae18018T, Škoda JS, a. s. (1995). (In Czech)

  17. Sýkora, M.: Reactor TVSA-T fuel assembly insertion, part 4, research report pp BZ1,2. Technical report, ČEZ ETE (2009). (In Czech)

  18. Yan, J., Yuan, K., Tatli, E., Karoutas, Z.: A new method to predict Grid-To-Rod Fretting in a PWR fuel assembly inlet region. Nucl. Eng. Des. 241(8), 2974–2982 (2011). doi:10.1016/j.nucengdes.2011.06.019. http://www.sciencedirect.com/science/article/pii/S0029549311005024

  19. Zeman, V., Hlaváč, Z.: Modelling of WWER 1000 type reactor vibration by means of decomposition method. In: Náprstek, J., Fischer, C. (eds.) Engineering Mechanics 2006: Book of extended abstracts, pp. 444–445. Institute of Theoretical and Applied Mechanics AS CR, Prague (2006). (Full text on CD-ROM in Czech)

    Google Scholar 

  20. Zeman, V., Hlaváč, Z.: Dynamic response of VVER 1000 type reactor excited by pressure pulsations. Eng. Mech. 15(6), 435–446 (2008)

    Google Scholar 

  21. Zeman, V., Hlaváč, Z.: Vibration of the package of rods linked by spacer grids. In: Vibration Problems ICOVP 2011, pp. 227–233. Springer (2011)

  22. Zeman, V., Hlaváč, Z.: Dynamic response of nuclear fuel assembly excited by pressure pulsations. Appl. Comput. Mech. 6(2), 219–230 (2012)

    Google Scholar 

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Acknowledgments

This work was supported by the European Regional Development Fund (ERDF), project “NTIS" European Centre of Excellence, CZ.1.05/1.1.00/02.0090 within the research project ČEZ - Fuel cycle of NPP coordinated by NRI Řež plc.

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Correspondence to Štěpán Dyk.

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Zeman, V., Dyk, Š. & Hlaváč, Z. Mathematical modelling of nonlinear vibration and fretting wear of the nuclear fuel rods. Arch Appl Mech 86, 657–668 (2016). https://doi.org/10.1007/s00419-015-1053-0

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