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Experience in Operating the BOR-60 Reactor

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Abstract

The results of 30 years of operation of BOR-60 are presented. The operating regimes and parameters for the core and main loops are presented. The operation of the main equipment and various systems is analyzed. A classification of the faults and failures is made. The advantages of currently operating counter-flow steam generators, from the standpoint of safety in the case of the appearance of an interloop leak, are indicated. Advances in sodium technology are briefly examined.

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Authors and Affiliations

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

    A. S. Korol'kov, G. I. Gadzhiev, V. N. Efimov & V. N. Marashev

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  1. A. S. Korol'kov
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  2. G. I. Gadzhiev
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  3. V. N. Efimov
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  4. V. N. Marashev
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Korol'kov, A.S., Gadzhiev, G.I., Efimov, V.N. et al. Experience in Operating the BOR-60 Reactor. Atomic Energy 91, 907–912 (2001). https://doi.org/10.1023/A:1014261723379

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  • DOI: https://doi.org/10.1023/A:1014261723379

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