Literature Cited
Yu. V. Vikhorev, V. A. Voznesenskii, V. P. Denisov, et al., “The VVÉR-1000 reactor facility-design characteristics and results of test run of fifth power plant at the Novovoronezh nuclear station and ways of further improving the facility,” At. Énerg.,50, No. 2, 87–93 (1981).
V. V. Lysenko, A. I. Musorin, A. I. Rymarenko, and S. G. Tsypin, Determination of the Nuclear-Physical and Heat-Physical Characteristics of a Water-Water Power Reactor with the Aid of Radiation Meters [in Russian], Energoatomizdat, Moscow (1985).
L. N. Bogachek, K. A. Gazaryan, V. V. Lysenko, et al., “A correlation-dispersion method for measuring the output of a water-water power reactor,” At. Énerg.,50, No. 6, 420–422 (1981).
L. N. Begachek, K. A. Gazaryan, V. V. Lysenko, et al., “Regulation of the energy release of a water-water power reactor by coolant activation,” in: Nucler Power Stations [in Russian], L. M. Voronin (ed.), No. 5, Énergoatomizdat, Moscow (1983), pp. 100–104.
A. A. Alekseev, L. N. Bogachek, K. A. Gazaryan, et al., “Measurement of the coolant flow rate in plant I of the Armyansk nuclear station using the radiation method,” in: Nuclear Power Stations [in Russian], L. M. Voronin (ed.), No. 5, Énergoatomizdat, Moscow (1983), pp. 97–100.
S. S. Kurochkin, The KAMAK-VEKTOR Systems [in Russian], Énergoizdat, Moscow (1981).
Additional information
Translated from Atomnaya Énergiya, Vol. 62, No. 5, pp. 307–311, May, 1987.
Rights and permissions
About this article
Cite this article
Agapov, S.A., Bogachek, L.N., Grubman, V.Y. et al. An automated radiation system for measuring the parameters of a VVÉR-1000 reactor. At Energy 62, 350–356 (1987). https://doi.org/10.1007/BF01125189
Received:
Issue Date:
DOI: https://doi.org/10.1007/BF01125189