Testing the debris fretting phenomenon of new perspective materials under LWR conditions

Authors

  • Ondřej Pašta Research Centre Řež s.r.o., Hlavní 130, 250 68 Husinec – Řež, Czech Republic https://orcid.org/0009-0000-7949-0409
  • Marcin Kopeć Research Centre Řež s.r.o., Hlavní 130, 250 68 Husinec – Řež, Czech Republic
  • Jakub Krejčí UJP Praha a.s., Nad Kamínkou 1345, 156 10 Praha – Zbraslav, Czech Republic https://orcid.org/0000-0003-3211-3328

DOI:

https://doi.org/10.14311/AP.2025.65.0696

Keywords:

fuel cladding, coating, Zr-alloys, CrNi alloy, FeCrAl alloy, debris fretting, nuclear fuel damage

Abstract

Despite decades of advancements and research aimed at improving fuel’s physical properties, fretting damage to fuel cladding remains a significant challenge. This study outlines the findings of experiments conducted on Zr-1%Nb alloy coated with protective layers composed of chromium-aluminium (CrAl) compounds and other new perspective materials, such as FeCrAl and CrNi alloys, at the Research Centre Řež. The experiments included debris-fretting tests performed under LWR conditions (320 °C and 15 MPa) and microscopic evaluations of groove depths. The primary goals were: (1) to evaluate the debris-fretting resistance of uncoated Zr-1%Nb samples compared to Zr-1%Nb with coatings and new alloys, and (2) to investigate the potential effects of coatings and new materials on the durability of fuel cladding. The conducted experiments and studies confirmed the benefits of the wear resistance of the ATF types of claddings in comparison to the standard Zr-1%Nb cladding material. Various parameters, such as wire wear and the influence of mutual position of the samples, were considered during the testing to provide the most precise insight into the wear resistance of the tested samples.

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References

A. Smirnov, V. Smirnov, D. Markov, et al. Post-irradiation examinations of WWER-440 FA provided with stainless steel spacer grids. In Fuel failure in water reactors: Causes and mitigation. Proceedings of a technical meeting, p. 164–170. International Atomic Energy Agency, 2003.

J. Y. Xu, J. L. Mo, B. Huang, et al. Reducing friction-induced vibration and noise by clearing wear debris from contact surface by blowing air and adding magnetic field. Wear 408–409:238–247, 2018. https://doi.org/10.1016/j.wear.2018.05.018

International Atomic Energy Agency. IAEATECDOC-1345. Fuel failure in water reactors: Causes and mitigation. In Proceedings of a Technical Meeting held in Bratislava, Slovakia, 17–21 June 2002. 2003.

R. Michal. Kurt Edsinger: EPRI and the zero fuel failures program. Nuclear News 53(13):40–43, 2010.

M. J. Pettigrew. The vibration behavior of nuclear fuel under reactor conditions. Nuclear Science and Engineering 114(3):179–189, 1993. https://doi.org/10.13182/NSE93-A24032

S. Kovács, J. Stabel, M. Ren, B. Ladouceur. Comparative study on rod fretting behavior of different spacer spring geometries. Wear 266(1):194–199, 2009. https://doi.org/10.1016/j.wear.2008.06.010

J. Yan, K. Yuan, E. Tatli, Z. Karoutas. A new method to predict Grid-To-Rod Fretting in a PWR fuel assembly inlet region. Nuclear Engineering and Design 241(8):2974–2982, 2011. https://doi.org/10.1016/j.nucengdes.2011.06.019

K.-T. Kim. A study on the grid-to-rod fretting wearinduced fuel failure observed in the 16×16KOFA fuel. Nuclear Engineering and Design 240(4):756–762, 2010. https://doi.org/10.1016/j.nucengdes.2009.12.014

J.-K. Park, S.-K. Lee, J.-H. Kim. Development of an evaluation method for nuclear fuel debris-filtering performance. Nuclear Engineering and Technology 50(5):738–744, 2018. https://doi.org/10.1016/j.net.2018.03.011

International Atomic Energy Agency. IAEA-TECDOC-1536. Status of small reactor designs without on-site refuelling, 2007.

L. Hallstadius, S. Johnson, E. Lahoda. Cladding for high performance fuel. Progress in Nuclear Energy 57:71–76, 2012. https://doi.org/10.1016/j.pnucene.2011.10.008

F. Franceschini. Advanced fuel cycles for light water reactors. Westinghouse Electric Company LLC, Pittsburgh, USA, 2011.

M. Kopeć, M. Malá, L. Cvrček, J. Krejčí. Debris fretting tests on standard and coated Zr-1%Nb cladding. In International conference on WWER fuel performance, modelling and experimental support, pp. 487–492. 2019.

M. Kopeć, M. Malá, L. Cvrček, J. Krejčí. Debris-fretting test of coated and uncoated Zr-1%Nb cladding. Acta Polytechnica CTU Proceedings 24:15–20, 2019. https://doi.org/10.14311/APP.2019.24.0015

P. Červenka, J. Krejčí, L. Cvrček, et al. Degradation of Cr-coated cladding under the simulated Loss-of-Coolant Accident phenomena. Acta Polytechnica CTU Proceedings 37:16–23, 2022. https://doi.org/10.14311/APP.2022.37.0016

O. Pašta, M. Kopeć, M. Malá, et al. Testování debris fretting jevu v podmínkách LWR [In Czech; Testing of the debris fretting phenomenon under LWR conditions]. In Jaderná energetika v pracích mladé generace – 2021: Sborník příspěvků z Mikulášského setkání Mladé generace ČNS, pp. 77–84. ČNS, Prague, Czech Republic, 2021. ISBN 978-80-02-03002-7.

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Published

2026-01-15

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Articles

How to Cite

Pašta, O., Kopeć, M., & Krejčí, J. (2026). Testing the debris fretting phenomenon of new perspective materials under LWR conditions. Acta Polytechnica, 65(6), 696–704. https://doi.org/10.14311/AP.2025.65.0696