Prediction of the Nuclear Fuel Rod Abrasion in the Probability Sense


Article Preview

The paper deals with the upper and lower limits estimation of the friction work and fretting wear in the contact of nuclear fuel rods with fuel assembly (FA) spacer grid cells. The friction work is deciding factor for the prediction of the fuel rod cladding abrasion caused by FA vibration. Design and operational parameters of the FA components are understood as random variables defined by mean values and standard deviations. The gradient and three sigma criterion approach is applied to the calculation of the upper and lower limits of the friction work and fretting wear in particular contact surfaces between the fuel rod cladding and some of spacer grid cells. The fuel assembly vibration is excited by pressure pulsations of the cooling liquid generated by main circulation pumps in the coolant loops of the NPP primary circuit. The method is applied for hexagonal type nuclear fuel assembly in the VVER type reactors.



Edited by:

Cyril Fischer




V. Zeman and Z. Hlaváč, "Prediction of the Nuclear Fuel Rod Abrasion in the Probability Sense", Applied Mechanics and Materials, Vol. 821, pp. 317-324, 2016

Online since:

January 2016




* - Corresponding Author

[1] L. Pečínka, J. Svoboda, V. Zeman: Fretting wear of the Zr fuel rod cladding, in: Proceedings of the 2014 22-nd International Conference of Nuclear Engineering ICONE22, (2014).

[2] J. Dupal, J.: Mechanics of stochastic systems. UWB, Pilsen, 2008 (in Czech).

[3] M. Kleiber, T. D. Hien: The Stochastic Finite Method. John Wiley & Sons, London, (1992).

[4] V. Zeman, Z. Hlaváč: Prediction of the nuclear fuel rod abrasion, Applied and Computational Mechanics, 7 (2013) 235-250.

[5] Z. Hlaváč, V. Zeman: Vibration of Nuclear Fuel Assemblies. LAP LAMBERT Academic Publishing, Saarbrücken, (2013).

[6] V. Zeman, Z. Hlaváč: Dynamic response of VVER 1000 type reactor excited by pressure pulsations, Engineering Mechanics, 15 (2008) 435-446.

[7] V. Zeman, Z. Hlaváč: Dynamic response of nuclear fuel assembly excited by pressure pulsations, Applied and Computational Mechanics, 6 (2012) 219-230.

[8] P. J. Blau: A multi-stage wear model for grid-to-rod fretting of nuclear fuel rods, Wear 313 (2014) 89-96.


[9] Y. H. Lee, H. K. Kim: Fretting wear behavior of a nuclear fuel rod under a simulated primary coolant condition, Wear 301 (2013) 569-574.


Fetching data from Crossref.
This may take some time to load.