Abstract
The results of an investigation of the material used for the VK-50 measurement channel, which showed no signs of unsealing when it was extracted after 25 years of operation, are presented. The results of metallographic and electron-microscope investigations and Auger-spectroscopy determination of the elemental composition are presented.
Intercyrstallite corrosion is found in the main metal of the measurement channel tube at the core-bottom level. A network of nonthrough, mainly longitudinal, cracks of an intercrystallite character, formed at the core-center and core-top levels and immediately under the reactor cover. The investigations show that the degree of corrosion damage to the channel material depends on the coolant density along the core height. Neutron irradiation can be a provoking factor but it is not the main factor making the main metal more likely to undergo corrosion cracking.
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References
Yu. D. Goncharenko, G. V. Filyakin, V. K. Shamardin, et al., “Study of the properties of the jacket material (0Kh18N10T steel) used for the cassette in a VK-50 reactor after 30 yr of operation,” in: 6th Interdepartmental Conference on Reactor Materials Engineering, Dimitrovgrad, September 11–15, 2000, Scientific-Research Institute of Nuclear Reactors (2001), Vol. 3, Pt. 1, pp. 49–68.
F. Garner, L. Greenwood, and H. Chung, “Irradiation-induced instability of MnS precipitates and its possible contribution to IASCC in light water reactors,” in: Proceedings of the 8th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Florida, USA, August 10–14, 1997, pp. 857–860.
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Translated from Atomnaya Énergiya, Vol. 100, No. 1, pp. 31–35, January, 2005.
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Filyakin, G.V., Shamardin, V.K. & Goncharenko, Y.D. Corrosion damage to Kh18N9T steel after 25 years of operation in the steam-water medium of a VK-50 boiling-water reactor. At Energy 100, 31–36 (2006). https://doi.org/10.1007/s10512-006-0046-z
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DOI: https://doi.org/10.1007/s10512-006-0046-z