Information is presented on the development of the main equipment of the BN-1200 advanced reactor facility: first- and second-loop main circulation pumps, intermediate heat exchanger, actuation mechanism of the cold filter-trap control and protection system, autonomous and air heat exchangers, steam generator. The approach to the development of the equipment is based on maximum use of the experience gained in operating BN-350 and -600 as well as experience in developing the BN-800 design, which gives a basis for ensuring reliable operation of the BN-1200 equipment. New solutions for improving the technical-economic indicators and increasing the safety of a power-generating unit, whose validation required R&D work, are examined at the same time.
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V. M. Poplavskii, B. A. Vasiliev, K. L. Suknev, et al., “BN-1800 advanced sodium-cooled fast reactor satisfying the requirements of 21st century nuclear power,” At. Énerg., 96, No. 5, 335–342 (2004).
V. I. Kostin and B. A. Vasiliev, “Problems of building BN-800 and possibilities for developing advanced fast reactors,” ibid., 102, No. 1, 21–26 (2007).
N. N. Oshkanov, M. V. Bakanov, and O. A. Potapov, “Experience in operating a BN-600 power-generating unit at the Beloyarskaya nuclear power plant,” ibid, 96, No. 5, 342–346 (2004).
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Translated from Atomnaya Énergiya, Vol. 108, No. 4, pp. 241–245, April, 2010.
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Vasiliev, B.A., Kamanin, Y.L., Gladkov, V.V. et al. Improvement of the equipment in fast-neutron reactor facilities. At Energy 108, 303–309 (2010). https://doi.org/10.1007/s10512-010-9293-0
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DOI: https://doi.org/10.1007/s10512-010-9293-0