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Please use this identifier to cite or link to this item: https://oldena.lpnu.ua/handle/ntb/40887
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dc.contributor.authorTrush, Vasyl-
dc.contributor.authorLuk’yanenko, Alexander-
dc.contributor.authorChvalbota, Volodymyr-
dc.date.accessioned2018-04-26T09:21:00Z-
dc.date.available2018-04-26T09:21:00Z-
dc.date.issued2016-
dc.identifier.citationTrush V. Oxidation and nitriding tubes of Zr-1%Nb zirconium alloy / Vasyl Trush, Alexander Luk’yanenko, Volodymyr Chvalbota // Litteris et Artibus : proceedings of the 6th International youth science forum, November 24–26, 2016, Lviv, Ukraine / Lviv Polytechnic National University. – Lviv : Lviv Polytechnic Publishing House, 2016. – P. 308–311. – Bibliography: 8 titles.uk_UA
dc.identifier.urihttps://ena.lpnu.ua/handle/ntb/40887-
dc.description.abstractThe work presents results of saturation of Zr-1% Nb tubes after processing in oxygen- and nitrogen- containing gas environments. The distribution of micro-hardness in the thickness of the tube and the thickness of the hardened layers, the weight gain was determined. It is found that the oxidation of the Zr-1%Nb alloy (Т = 650°С, РО2=2.6·10-1 Pа, τ = 3…20 h) makes a greater weight gain than nitriding (Т = 650°С, τ = 5…20 h). The state of the surface of the inside and outside of Zr-1%Nb tubes for fuel cladding depending of the processings time was shown. The differences in saturation of outside and inside of the tube was showed. In particular, the hardness of internal surface of the tube is smaller relative to the outside after oxidizing and nitriding was found. The results of study of the outer and inner surface of fuel cladding in contact with gaseous environment containing oxygen and nitrogen are interesting for investigators of reactor materials.uk_UA
dc.language.isoenuk_UA
dc.publisherLviv Polytechnic Publishing Houseuk_UA
dc.subjectzirconium alloyuk_UA
dc.subjectoxygenuk_UA
dc.subjectnirtrogenuk_UA
dc.subjectsurface hardnesuk_UA
dc.subjecthardened layeruk_UA
dc.subjectweight gainuk_UA
dc.titleOxidation and nitriding tubes of Zr-1%Nb zirconium alloyuk_UA
dc.typeConference Abstractuk_UA
dc.contributor.affiliationKarpenko Physico-Mechanical institute of the NASUuk_UA
dc.contributor.affiliationLviv Polytechnic National Universityuk_UA
dc.coverage.countryUAuk_UA
dc.format.pages308-311-
dc.relation.referencesen[1] F. Hideki, T. Kazuhiro, Ya. Yoshito, "Application of titanium and its alloys for automobile parts", Nippon Steel Technical Report. – 2003. – No 88, pp. 70–75. [2] G. Lutjering, J.C. Williams, "Titanium", 2nd edition, Springer-Verlag Berlin Heidelberg, 2007. – 438 p. a b Fig. 8. The outer (a) and inner (b) surfaces' view of tubes of Zr-1%Nb alloy after processing at CTP mode P7 [3] "Quality and reliability aspects in nuclear power reactor fuel engineering", Vienna: International Atomic Energy Agency, 2015. – 207 p. [4] T.R. Allen, R.J.M Konings, A.T. Motta (2012) "Corrosion of Zirconium Alloys", In: Konings R.J.M., (ed.) Comprehensive Nuclear Materials. – 2012. – Vol. 5. – P. 49-68. [5] N. Selmi, A. Sary, "Noureddine Selmi Stady of oxidation kinetics in air of Zircaloy -4 by in sity X-ray diffraction", Advances in materials physics and chemistry. 2013, 3, рр. 168-173 [6] D. Duhlas, "Metallovedenye tsyrkonyia" M., Atomyzdat, 1975, р. 360. [7] V.M. Azhazha, B.V. Borts, I.M. Butenko ta inshi. "Vyrobnytstvo partii trubnykh zahotovok treks-trub ta vyhotovlennia doslidno-promyslovoi partii tvelnykh trub zi splavu Zr–1Nb iz vitchyznianoi syrovyny", Nauka ta innovatsii, –2006. № 4. pp. 64–76. [8] N.Y. Yshchenko, Y.A. Petelhuzov, E.A. Slabospytskaia, R.L. Vasylenko "Vlyianye vysokotemperatrunoho otzhyha na strukturu obolochek tvelov yz splava tsyrkonyia s 1%Nb", VANT, Seryia: Fyzyka radyatsyonnykh povrezhdenyi y radyatsyonnoe materyalovedenye, (88), №5, 2005, pp.115-120.uk_UA
dc.citation.conferenceLitteris et Artibus-
dc.coverage.placenameLvivuk_UA
Appears in Collections:Litteris et Artibus. – 2016 р.

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