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State of SBYa Alloy after 31 Years of Operation in a VK-50 Reactor

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Abstract

The purpose of this work was to investigate the structural state and composition of an SBYa alloy (with natural boron content 1.5%) after prolonged (31 yr) operation in a VK-50 reactor up to complete 10B burnup. It was found that as a result of irradiation the impact viscosity of the alloy decreased from 29 to 12–20 J/cm2. The two-phase structure of the alloy and the elemental composition of the phases after irradiation remained unchanged. As a result of the formation of helium pores in both phases, the alloy density decreased by 5.1%. Two types of operational damage to the alloy were discovered: cracking and focal corrosion on surfaces in contact with water. It was shown that the corrosion resistance of the boron-containing phase is lower than that of the austenite phase.

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Authors and Affiliations

  1. State Science Center of the Russian Federation – Scientific-Research Institute of Nuclear Reactors, Russia

    A. A. Khudyakov, Z. E. Ostrovskii, V. D. Risovanyi, A. V. Zakharov & V. V. Yakovlev

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  1. A. A. Khudyakov
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  2. Z. E. Ostrovskii
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  3. V. D. Risovanyi
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  4. A. V. Zakharov
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  5. V. V. Yakovlev
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Khudyakov, A.A., Ostrovskii, Z.E., Risovanyi, V.D. et al. State of SBYa Alloy after 31 Years of Operation in a VK-50 Reactor. Atomic Energy 92, 124–128 (2002). https://doi.org/10.1023/A:1015870505018

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  • DOI: https://doi.org/10.1023/A:1015870505018

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