Abstract
We describe the methods and results of investigation of the characteristics of strength and plasticity of a pilot batch of tubes made of KTTs-110 zirconium alloy under the conditions of short- and long-term static loading. The obtained results are compared with the same characteristics of É-110 alloy extensively used in the active zones of WWÉR-1000-type nuclear reactors.
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REFERENCES
V. S. Vakhrusheva, "The state of development of technological procedures and the organization of production of tubes of KTTs-110 zirconium alloy (used as shells of heating elements) in the Ukraine," Vopr. Atom. Nauk. Tekh. Ser. Phys. Radiats. Povrezhd. Radiats. Materialoved., Issues 1 (73), 2 (74), 95–100 (1999).
A. S. Zaimovskii, A. V. Nikulina, and I. G. Reshetnikov, Zirconium Alloys in Nuclear Power Engineering [in Russian], Énergoatomizdat, Moscow (1981).
V. V. Klyuev (Ed.), Testing Equipment. A Handbook [in Russian], Vol. 2, Mashinostroenie, Moscow (1982).
V. K. Kharchenko, "On the high-temperature strength of refractory materials," Probl. Prochn., No. 10, 94–103 (1980).
DSTU 2528-94. A Method for Tensile Testing of Annular Specimens under Conditions of Heating [in Russian], Introduced on 01.07.1995.
I. M. Neklyudov, L. S. Ozhigov, V. I. Savchenko, et al., "Evaluation of the characteristics of the plasticity of circular specimens of zirconium alloys in the transverse direction," Probl. Prochn., No. 2, 137–141 (2001).
OI 001.325-91. Experimental Procedure of Evaluation of the Characteristics of Mechanical Properties of Annular Specimens of Tubes According to TU 95.405-89 in Tension [in Russian], Introduced on 19.09.1991.
M. N. Stepnov, Statistical Processing of the Results of Mechanical Tests [in Russian], Mashinostroenie, Moscow (1972).
V. N. Kiselevskii, V. V. Kovalev, and G. S. Rossikhin, "Kinetics of fracture of the shells of fuel elements made of zirconium alloys in iodine media," Probl. Prochn., No. 3, 30–39 (1994).
G. P. Kobylyanskii and A. E. Novoselov, Radiation Resistance of Zirconium and Alloys Based on Zirconium [in Russian], Dimitrovgrad (1996).
V. N. Kiselevskii, Strength of Structural Materials of Nuclear Reactors [in Russian], Naukova Dumka, Kiev (1990).
P. Hofmann and J. Spino, "Chemical aspects of iodine-induced stress corrosion cracking failure of Zircaloy-4 tubing above 500°C," J. Nucl. Mater., 114, 50–65 (1983).
D. B. Knorr, R. M. Pelloux, and L. F. P. van Swam, "Effects of material condition on the iodine SCC susceptibility of Zircaloy-2 cladding," J. Nucl. Mater., 110, Nos. 2-3, 230–245 (1982).
V. N. Kiselevskii, V. V. Kovalev, V. A. Stepanenko, et al., "Stress-corrosion cracking resistance of a zirconium alloy," Probl. Prochn., No. 2, 122–130 (1998).
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Kovalev, V.V., Kisilevskii, V.N., Borisenko, V.A. et al. High-Temperature Strength of KTTs-110 Zirconium Alloy. Strength of Materials 36, 314–320 (2004). https://doi.org/10.1023/B:STOM.0000035765.22963.ad
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DOI: https://doi.org/10.1023/B:STOM.0000035765.22963.ad