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Selecting main technical solutions for heat supply systems equipped with nuclear cogeneration stations

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Abstract

Methodical principles for determining the yearly quantities of heat supplied from a nuclear cogeneration station are described, results from an analysis for selecting the optimal design cogeneration ratio and the parameters of heat carrier are presented, and matters pertinent to the operational reliability and safety of heat supply systems equipped with nuclear cogeneration stations are considered.

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References

  1. L. A. Melent’ev and I. A. Stolyarova, “The Parameters of Nuclear Cogeneration Systems,” Teploenergetika, No. 12, 10–15 (1978) [Therm. Eng., No. 12 (1978)].

  2. L. S. Khrilev, District Heating Cogeneration Systems (Energoatomizdat, Moscow, 1988) [in Russian].

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  3. Yu. N. Kuznetsov, “The Results of Feasibility Study of Cogeneration NPP with Innovative VK-300 Simplified Boiling Water Reactor,” in Proceedings of the International Congress on Advances in Nuclear Power Plants, Reno, NV, USA, June 4–8, 2006, Paper 6014, pp. 1–6.

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Original Russian Text © I.A. Smirnov, K.S. Svetlov, L.S. Khrilev, 2008, published in Teploenergetika.

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Smirnov, I.A., Svetlov, K.S. & Khrilev, L.S. Selecting main technical solutions for heat supply systems equipped with nuclear cogeneration stations. Therm. Eng. 55, 939–946 (2008). https://doi.org/10.1134/S0040601508110050

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  • DOI: https://doi.org/10.1134/S0040601508110050

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