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Method for diagnostics of coolant leaks in the first loop into the boiler water of steam generators in nuclear power plants with VVÉR-440 and -1000 reactors

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Literature Cited

  1. E. A. Ivanov, I. V. Pyrkov, and L. P. Kham'yanov, “Model of radionuclide accumulation in the boiler water of the steam generators of nuclear power plants with VVÉR-440 and -1000 reactors,” this issue, pp. 58–63.

  2. J. Seber, Linear Regression Analysis [Russian translation], Mir, Moscow (1980).

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  3. Circular on “Admissible magnitude and method for monitoring leakage of first-loop coolant and standardization of radionuclide activity of technological media of the second loop in nuclear power plants with VVÉR-440 and VVÉR-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. 1. pp. 51–58, July, 1994.

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Ivanov, E.A., Pyrkov, I.V. & Kham'yanov, L.P. Method for diagnostics of coolant leaks in the first loop into the boiler water of steam generators in nuclear power plants with VVÉR-440 and -1000 reactors. At Energy 77, 543–548 (1994). https://doi.org/10.1007/BF02408213

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  • DOI: https://doi.org/10.1007/BF02408213

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