The first reactor tests and post-reactor studies of fuel elements with cladding made from the zirconium alloys E-636M, E-635opt, and E-635M1, developed at VNIINM, have been conducted. The purpose of the studies was to search for alloys of the type E-635 that surpass the base alloy in terms of resistance to corrosion and hydration. The studies make it possible to recommend the alloys E-635M and E-635opt for use as cladding of the fuel elements in extended-life cores.
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References
A. V. Nikulina, “Nodular corrosion of zirconium articles,” Vopr. At. Nauki Tekhn. Ser. Materialoved. Nov. Mater., No. 1(72), 79–89 (2012).
A. V. Nikulina, V. A. Markelov, M. M. Peregud, et al., “Irradiation-induced microstructural changes in Zr–1%Sn–1%Nb–0.4%Fe,” J. Nucl. Mater., 238, 205– 210 (1996).
A. V. Vatulin, I. N. Volkova, and A. E. Novoselov, “Corrosion of the alloy E-635 in the core of a nuclear icebreaker,” At. Energ., 111, No. 4, 235–237 (2011).
G. V. Kulakov, A. V. Vatulin, Yu. V. Konovalov, et al., “Analysis of the effect of the stress-strain state of the radiated fuel element cladding made of zirconium alloy on hydride orientation,” At. Energ., 122, No. 2, 73–77 (2017).
A. V. Nikulina, “Zirconium alloys in nuclear power,” Metalloved. Term. Obrab. Met., No. 11, 8–12 (2004).
V. N. Shishov, “Evolution of the microstructure and the deformation stability of the alloys ZR–Nb–(Fe–Sn–O) under irradiation,” Vopr. At. Nauki Tekhn. Ser. Materialoved. Nov. Mater., No. 1(72), 90–106 (2012).
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Translated from Atomnaya Énergiya, Vol. 123, No. 6, pp. 329–334, December, 2017.
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Kulakov, G.V., Konovalov, Y.V., Kosaurov, A.A. et al. Behavior of Modified Zirconium-Alloy Fuel-Element Cladding Under Irradiation. At Energy 123, 399–405 (2018). https://doi.org/10.1007/s10512-018-0359-8
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DOI: https://doi.org/10.1007/s10512-018-0359-8