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COMPOSITES AND MULTIPURPOSE COATINGS
Название Influence of technology of obtaining chromium coating on cladding tubes from Zr – 1% Nb – (O, Fe) alloy on change of its structure during air oxidation at temperatures 400–1150 oC
DOI 10.17580/tsm.2020.02.09
Автор Isaenkova M. G., Perlovich Yu. A., Stolbov S. D., Klyukova K. E., Fesenko V. A., Berlin E. V.
Информация об авторе

National Research Nuclear University “MEPhI”, Moscow, Russia:

M. G. Isaenkova, Professor, the chair “Physical problems of material science”, Doctor of Physical and Mathematical Sciences, e-mail: isamarg@mail.ru
Yu. A. Perlovich, Professor, Doctor of Physical and Mathematical Sciences
S. D. Stolbov, Post-graduate Student
K. E. Klyukova, Post-graduate Student
V. A. Fesenko, Scientific Researcher

 

Vacuum Technology Laboratory LLC, Zelenograd, Moscow, Russia:
E. V. Berlin, General Designer

Реферат

This paper compares the corrosion behavior of two chromium coatings obtained by different technological conditions. Depending on the process characteristics of creating coatings, a different structure was formed, which characterized by different orientations and grain sizes. The main differences of the investigated coatings were as follows: coating No. 1 was 9–10 μm thick, characterized by 0.2 μm columnar crystals and {111} <112> strict orientation throughout its thickness; coating No. 2 had a thickness of 12–14 μm, the size of the columnar crystals was 0.5 μm and their orientation was {111} <112> and {100} <001>. The coatings also differed in the level of compressive tangential macrostresses on the outer surface: in the first one, 1000 MPa, and in the second, only 490 MPa, which indicated the possibility of cracks presence in it. The presence of cracks was confirmed by metallographic images. Oxidation of cladding tubes with chromium coatings was carried out by their annealing in air in the temperature range of 400–1150 oC for 1 hour. As a result of electron microscopic study of over the cross section elements distribution of oxidized samples, the main differences in the coatings oxidation kinetics obtained in different modes were established. In the initial state, both coatings interact with the substrate without the formation of intermediate phases, the chromium layer is replaced by a layer of zirconium alloy. In both cases, the transition zone is 2–3 microns. After annealing in air at a temperature of 1100 oC for 1 h, an intermetallic layer (Zr, Nb)Cr2 with a thickness of 2–3 μm is formed between the coating and the substrate. Intermetallide identified by synchrotron diffraction coating study. The first coating changes its thickness to 5–6 microns, while on the surface it is not possible to detect the oxide phase. In the case of the second coating oxidation, a 3–4 μm layer of the oxide phase is observed, easily identified by X-ray and electron microscopic methods, which leads to a reduction in the thickness of the chrome coating. The pore distribution is also interesting: in the case of the first coating, the pores are located at the boundary of the intermetallic and chrome layers, and in the case of the second coating, the pores are distributed over the cross section of the chromium layer and in the oxide layers. The oxide layer thickness from the inner surface of the cladding tube is about 250 microns. The chrome coating, in the absence of cracks in it, reliably protects the cladding tube from oxygen. In the absence of cracks in the chrome coating, it reliably protects the cladding tube from oxygen. The presence of pores is due to differences in the temperature expansion of layers consisting of different metals.
The present work was carried out under Governmental Support of Competitive Growth Program of NRNU MEPhI (agreement No. 02.a03.21.0005).

Ключевые слова Fuel cladding, E110 alloy, chrome coating, crystallographic texture, oxidation, element analysis
Библиографический список

1. Koo Y.-H., Yang J.-H., Park J.-Y., Kim K.-S., Kim D.-J. et al. KAERI’s Development of LWR Accident-Tolerant Fuel. Journal of Nuclear Technology. 2014. Vol. 186, Iss. 2. pp. 295–304.
2. Kim H.-G., Kim I.-H., Jung Y.-I., Park D.-J., Yang J.-H. et al. Development of Surface Modified Zr Cladding by Coating Technology for ATF. Conference Top Fuel 2016. Boise, 11–15 September 2016. pp. 1157–1163.
3. Kim H.-G., Yang J.-H., Kim W.-J., Koo Y.-H. Development status of accident-tolerant fuel for light water reactors in Korea. Nuclear Engineering and Technology. 2016. Vol. 48, No. 1. pp. 1–15.
4. Shishov V. N., Peregud M. M., Nikulina A. V., Shebaldov P. V., Tselishchev A. V. et al. Influence of Zirconium Alloy Chemical Composition on Microstructure Formation and Irradiation Growth. 13th International Symposium on Zirconium in the Nuclear Industry. Annecy, France, 2001. pp. 758–779.
5. Petelguzov I. А. Influence of aluminum and chromium covering on oxidation zirconium and some his alloys. Problems of Atomic Science and Technology. 2012. No. 2. pp. 114–119.
6. Kopanetz I. E., Tolstolutskaya G. D., Nikitin A. V., Bilous V. A., Kuprin A. S. et al. The effect of Cr, Cr–N and Cr–Ox coatings on deuterium retention and penetration in zirconium alloy Zr – 1Nb. Problems of Atomic Science and Technology. 2015. No. 5. pp. 81–86.
7. Kuprin A. S., Belous V. А., Voyevodin V. N., Bryk V. V., Vasilenko R. L. et al. Vacuum-arc chromium-based coatings for protection of zirconium alloys from the high-temperature oxidation in air. Journal of Nuclear Materials. 2015. Vol. 465. pp. 400–406.
8. Kuprin A. S., Belous V. A., Bryk V. V., Vasilenko R. L., Voyevodin V. N. et al. Vacuum-arc chromium coatings for Zr-1Nb alloy protection against hightemperature oxidation in air. Problems of Atomic Science and Technology. 2015. No. 2. pp. 111–118.
9. Kuprin A. S., Belous V. A., Voyevodin V. N., Bryk V. V., Vasilenko R. L. et al. High-temperature air oxidation of E110 and Zr – 1Nb alloys claddings with coatings. Problems of Atomic Science and Technology. 2014. No. 1. pp. 126–132.
10. Belous V. A., Vygov P. N., Kuprin A. S., Leonov S. A., Nosov G. I. et al. Mechanical characteristics of Zr1Nb alloy tube after deposition of ionplasma coatings. Problems of Atomic Science and Technology. 2013. No. 2. pp. 140–143.
11. Park J. H., Kim H. G., Park J. Y., Jung Y. I., Park D. J. et al. High temperature steam-oxidation behavior of arc ion plated Cr coatings for accident fuel claddings. Surface and Coating Technology. 2015. Vol. 280. pp. 256–259.
12. Kim H. G., Kim I. H., Jung Y. I., Park D. J., Park J. Y. et al. Adhesion property and high-temperature oxidation behaviour of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating. Journal of Nucear Materials. 2015. Vol. 465. pp. 531–539.
13. Bunnell L. R., Mellinger G. B., Bates J. L., Harm C. R. High-temperature properties of zircaloy-oxygen alloys. Palo Alto : Electric Power Research Institute, 1977.
14. Bunnell L. R., Bates J. L., Mellinger G. B. Some High-Temperature Properties of Zircaloy-oxygen Alloys. Journal of Nuclear Materials. 1983. Vol. 116, Iss. 2-3. pp. 219–232.
15. Fong R. W. L., Fazeli F., Smith T. Thermal Expansion Anisotropy of Zr – 2,5Nb Pressure Tube Material on Heating to 1100 oC. 35th Annual Conference of the Canadian Nuclear Society & 38th CNS/CNA Student Conference 2015. Vol. 1. pp. 636–647.
16. Berlin E. V., Grigoriev V. Yu., Ivanov A. V., Isaenkova M. G., Klyukova K. E. et al. Structure of the protective chromium coating obtained by a thermal evaporation method in a magnetron discharge on the cladding tube from E110 alloy. Tsvetnye metally. 2019. No. 4. pp. 33–40.
17. Ivanov A. V., Kuraev A. Yu., Malakhov A. A., Lerner A. E., Luzan Yu. V. The study properties of protective chrome coating on the samplessimulators of WWER fuel rods. Problems of Atomic Science and Technology. Series: Materials Technology and New Materials. 2018. No. 3. pp. 116–130.
18. Idarraga-Trujillo I., Le Flem M., Brachet J.-C., Le Saux M., Hamon D. et al. Assessment at CEA of coated nuclear fuel cladding for LWRs with increased margins in loca and beyond loca conditions. Proceedings of TopFuel 2013. Charlotte, North Carolina, USA, 15–19 September 2013. pp. 860–867.
19. Brachet J.-C., Idarraga-Trujillo I., Flem M. L., Saux M. L., Vandenberghe V. et al. Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors. Journal of Nuclear Materials. 2019. Vol. 517. pp. 268–285.
20. Berlin E. V., Grigorev V. Yu. Plasma generator. Patent 2503079 RU. Published: 27.12.2013. Bulletin No. 30.
21. Khodachenko G. V., Stepanova T. V. et al. Method of combined ionplasma treatment of products out of aluminium alloys. Patent 2566232 RU. Published: 20.10.2015, Bulletin No. 29.
22. Perlovich Y., Isaenkova M., Fesenko V. Modern methods of experimental construction of texture complete direct pole figures by using X-ray data. IOP Conf. Series: Materials Science and Engineering. 2016. Vol. 130. pp. 012055.
23. Perlovich Y., Isaenkova M., Bunge H.-J. The Fullest Description of the Structure of Textured Metal Materials with Generalized Pole Figures: the Example of Rolled Zr Alloys. Materials Science Forum. 2001. Vol. 378–381. pp. 180–185.
24. Gorelik S. S., Skakov Yu. A., Rastorguev L. N. X-ray and electron-optical analysis. Moscow : MISiS, 2002. 366 p.
25. Lyakishev N. P. State diagrams of binary metal systems : a reference book. In 3 vols. Vol. 2. Moscow : Mashinostroenie, 1997. 1024 p.
26. Lu H.-J., Wu H., Zou N., Lu X.-G., He Y.-L., Morgan D. First-principles investigation on diffusion mechanism of alloying elements in dilute Zr alloys. Acta Materialia. 2018. Vol. 154. pp. 161–171.
27. Neumann G., Tuijn C. Self-diffusion and impurity diffusion in pure metals: handbook of experimental data. Oxford : Elsevier, 2008. 360 p.

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