Conclusions
There is a basic possibility to raise the maximum power of a unit containing the VVÉR-1000 reactor in the course of the fuel charge burn-up and with lowering the coefficient of the energy-release nonuniformity in the reactor core. It is more advantageous economically to obtain additional power in carrying the peak load. With the duration of such operating conditions for 1000–2000 h/yr savings can amounts to 1–4 million rubles per year per 100 MW of additional power when compared to peaking GTP.
It is necessary to analyze in more detail the safety as well as technical and economic indexes of the VVÉR-1000 and of the entire power unit both under normal operating conditions and in emergency situation for the proposed elevated power mode.
It is necessary to develop a procedure of experimental substantiation of a possible forcing level for the operating units of the NPS containing a VVÉR. The interested agencies should be involved in this development. Technical and economic advisability of making up a set of power-unit equipment suitable to carry short load peaks and prolonged elevation of the electric loads in the EPS should be determined on this basis and changes and additions should be introduced when developing new designs.
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Literature Cited
A. M. Alpatov, “Module heat-exchange crisis: subprogram for determination of the conditions of heat-emission crisis at boiling in the VVÉR core channels in steady-state and transitional modes,” Preprint I. V. Kurchatov IAÉ. No. 9-2475, Moscow (1975).
A. I. Abramov, A. G. Il'chenko, and V. S. Kaekin, “Heat supply from the first loop of the VVÉR reactors for serving the heat load of an atomic central heating-and-power plant,” in: Improvement of the Reliability and Efficiency of Thermal and Nuclear Power Stations [in Russian], MÉI, Moscow (1980), pp. 66–67.
L. M. Voronin, Nuclear Power Stations' Operations and Maintenance Features [in Russian] Énergoizdat, Moscow (1981).
R. Z. Aminov, V. A. Khrustalev, and A. A. Luk'yanov, “Method of obtaining additional power in atomic steam-turbine plant,” Inventors' Certificate No. 917645, Byull. Izobret., No. 33, 1983.
R. Z. Aminov, V. A. Khrustalev, and B. F. Kalugin, “Steam-turbine plant,” Inventors' Certificate No. 1067232, Byull. Izobret., No. 2, 1984.
A. S. Monakhov, V. A. Zverev, V. G. Luchkin, et al., “Substantiation of complexone water regime of steam generators in two-circuit nuclear power stations,” Teploenergetika, No. 2, 41–43 (1984).
T. Kh. Margulova, “Improvement of separation characteristics of steam generators of nuclear power stations containing water-cooled water-moderated reactors,” Teploenergetika, No. 11, 6–7 (1984).
G. I. Konovalov, V. A. Kanaev, F. M. Sukharev, et al., “Thermal tests of the K-500-60/1500 turbine plant,” Teploenergetika, No. 4, 4–9 (1984).
L. A. Melent'ev, Optimization of Development and Control of Power Industry's Large Systems [in Russian], Vysshaya Shkola, Moscow (1982).
B. M. Troyanovskii, Turbines for Nuclear Power Stations [in Russian], Énergiya, Moscow (1978).
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Translated from Atomnaya Énergiya, Vol. 61, No. 6, pp. 397–401, December, 1986.
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Aminov, R.Z., Khrustalev, V.A., Serdobintsev, A.A. et al. Efficiency of producing additional power in units of nuclear power stations containing water-cooled-water-moderated reactors. At Energy 61, 975–980 (1986). https://doi.org/10.1007/BF01127261
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DOI: https://doi.org/10.1007/BF01127261