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Konferencja
International Conference on Development and Applications of Nuclear Technologies NUTECH 2023 (22-24 September 2023 ; Krakow, Poland)
Języki publikacji
Abstrakty
Zirconium alloys are used as a cladding material for fuel elements in nuclear reactors. In the case of severe accident conditions, the possible rapid oxidation of zirconium in steam or/and air may result in intense hydrogen generation and hydrogen–oxide mixture explosion. Advanced technologies for increasing the corrosion resistance of claddings are being investigated in two directions: (a) protective coatings on Zr alloys and (b) the use of new materials for claddings. Coatings with silicon may provide a more protective barrier than the ZrO2 films formed on an alloy cladding during nuclear plant operations. These coatings may also serve as a protective barrier during high-temperature accidents. The current work aimed at developing protective coatings with silicon on zirconium alloys. Multielemental Zr–Si–Cr coatings were formed on Zry-2 alloy using the physical vapor deposition (PVD) method. Long-term oxidation tests were carried out under the following conditions: 360°C/195 bar/63 days/water-simulating PWR water. Obtained results show the protective character of formed layers. The material in the form of silicon carbide grains covered with yttrium–aluminum garnet (SiC + YAG) was prepared using the sol–gel method. The formed powder is the main component for coating formation on Zr–1Nb alloy using the method of suspension plasma spraying (SPS).
Słowa kluczowe
Czasopismo
Rocznik
Tom
Strony
125--128
Opis fizyczny
Bibliogr. 14 poz., rys.
Twórcy
autor
- Institute of Nuclear Chemistry and Technology Dorodna 16 St., 03-195 Warsaw, Poland
autor
- Institute of Nuclear Chemistry and Technology Dorodna 16 St., 03-195 Warsaw, Poland
autor
- Wrocław University of Science and Technology Wrocław, Poland
autor
- Institute of Nuclear Chemistry and Technology Dorodna 16 St., 03-195 Warsaw, Poland
autor
- Łukasiewicz Research Network – The Institute for Sustainable Technologies, Radom, Poland
Bibliografia
- 1. Terrani, K. A., Zinkle, S. J., & Snead, L. L. (2014). Advanced oxidation-resistant iron-based alloys for LWR fuel cladding. J. Nucl. Mater., 448(1/3), 420–435. https://doi.org/10.1016/j.jnucmat.2013.12.005.
- 2. Zinkle, S. J., Terrani, K. A., Gehin, J. C., Ott, L. J., & Sneadf, L. L. (2014). Accident tolerant fuels for LWRs: A perspective. J. Nucl. Mater., 448(1/3), 374–379. https://doi.org/10.1016/j.jnucmat.2013.12.005.
- 3. Kashkarov, E., Afornu, B., Sidelev, D., Krinitcyn, M., Gouws, V., & Lider, A. (2021). Recent advances in protective coatings for accident tolerant Zr-based fuel claddings. Coatings, 11(5), 557. https://doi. org/10.3390/coatings11050557.
- 4. Kim, H. G., Kim, I. H., Jung, Y. I., Park, D. J., Park, J. Y., & Koo, Y. H. (2014). Application of coating technology on zirconium-based alloy to decrease hightemperature oxidation. In C. Comstock & P. Barberis (Eds.), 17th International Symposium – Zirconium in the nuclear industry (pp. 346–369). West Conshohocken, PA: ASTM International.
- 5. Park, D. J., Kim, H. G., Jung, Y., Park, J. H., Yang, J. H., & Koo, Y. H. (2016). Behaviour of an improved Zr fuel cladding with oxidation resistant coating under loss-of-coolant accident conditions. J. Nucl. Mater., 482, 75–82. https://doi.org/10.1016/j.jnucmat.2016.10.021.
- 6. Terrani, K. A., Parish, C. M., Shin, D., & Pint, B. A. (2013). Protection of zirconium by alumina- and chromia-forming iron alloys under high-temperature steam exposure. J. Nucl. Mater., 438, 64–71. https://doi.org/10.1016/j.jnucmat.2013.03.006.
- 7. Brachet, J. C., Le Saux, M., Le Flem, M., Urvoy, S., Rouesne, E., Guilbert, T., Cobac, C., Lahogue, F., Rousselot, J., Tupin, M., Billaud, P., Hossepied, B. C., Schuster, F., Lomello, F., Billard, A., Velisa, G., Monsifrot, E., Bischoff, J., & Ambard, A. (2015). Ongoing studies at CEA on chromium coated zirconium based nuclear fuel claddings for enhanced accident tolerant LWRs fuel. In Proceedings of TopFuel 2015, (pp. 31–38), September 13–19, Zurich, Switzerland.
- 8. Tang, C., Stueber, M., Seifert, H. J., & Steinbrueck, M. (2017). Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings. Corros. Rev., 35, 141–165. https://doi.org/10.1515/corrrev-2017-0010.
- 9. Hui, R., Cook, W., Sun, C., Xie, Y., Yoo, P., Miles, J., Olive, R., Li, J., Zheng, W., & Zhang, L. (2011). Deposition, characterization and performance evaluation of ceramic coatings on metallic substrates for supercritical water-cooled reactors. Surf. Coat. Technol., 205, 3512–3519. https://doi.org/10.1016/surfcoat.2010.12.017.
- 10. Zeng, Y., Xiong, X., Guo, S., & Zhang, W. (2013). SiC/SiC–YAG–YSZ oxidation protective coatings for carbon/carbon composites. Corros. Sci., 70, 68–73. https://doi.org/10.1016/j.corsci.2013.01.013.
- 11. Mondal, K., Nunez, L. III, Downey, C. M., & van Rooyen, I. J. (2021). Thermal barrier coatings overview: Design, manufacturing, and applications in high-temperature industries. Ind. Eng. Chem. Res., 60(17), 6061–6077. https://doi.org/10.1021/acs.iecr.1c00788.
- 12. Rincon, A., Pala, Z., & Hussain, T. (2020). A suspension high velocity oxy-fuel thermal spray manufacturing route for silicon carbide – YAG composite coatings. Mater. Lett., 281, 128601–128604. https://doi.org/10.1016/j.matlet.2020.128601.
- 13. Sartowska, B., Starosta, W., Walis, L., Smolik, J., & Panczyk, E. (2022). Multi-elemental coatings on zirconium alloy for corrosion resistance improvement. Coatings, 12, 1112. https://doi.org/10.3390/coatings12081112.
- 14. Deptuła, A., Hahn, H., Rebandel, J., Drozda, W., & Kalinowski, B. (1977). Polish Patent No. 83484. Warsaw: The Patent Office of the Republic of Poland.
Uwagi
Opracowanie rekordu ze środków MNiSW, umowa nr POPUL/SP/0154/2024/02 w ramach programu "Społeczna odpowiedzialność nauki II" - moduł: Popularyzacja nauki (2025).
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-ac19c1bc-e048-4be1-a534-f56d8fb3174e
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