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Snesk — program for calculating first-loop coolant leaks into the boiler water of the steam generators of a nuclear power plant with a VVÉR reactor

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Literature Cited

  1. E. A. Ivanov, I. V. Pyrkov, and L. P. Kham'yanov, "Model of accumulation of radionuclides in the boiler water of the steam generators of nuclear power plants with VVÉR-440 and -1000 reactors," At. Énerg.,77, No. 1, 58–63 (1994).

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  2. E. A. Ivanov, I. B. Pyrkov, and L. P. Kham'yanov, "Method of diagnostics of first-loop coolant leaks into the boiler water of steam generators in nuclear power plants with VVÉR-400 and -1000 reactors," At. Énerg.,77, No. 1, 51–58 (1994).

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  3. Circular "On the admissible magnitude and method for monitoring first-loop coolant leaks and normalization of the radionuclide activity of the technological media in the second loop in nuclear power plants with VVÉR-400 and -1000 reactors," [in Russian], Minatoménergoprom SSSR, Moscow (1991).

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All-Union Scientific-Research Institute of Nuclear Power Plants. Translated from Atomnaya Énergiya, Vol. 77. No. 6, pp. 457–458, December, 1994.

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Ivanov, E.A., Pyrkov, I.V. & Kham'yanov, L.P. Snesk — program for calculating first-loop coolant leaks into the boiler water of the steam generators of a nuclear power plant with a VVÉR reactor. At Energy 77, 944–945 (1994). https://doi.org/10.1007/BF02415549

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  • DOI: https://doi.org/10.1007/BF02415549

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