Literature Cited
F. M. Mitenkov, V. V. Egorov, V. S. Kuul', et al., “The concept of reactor safety in nuclear heat-supply stations,” At. Énerg.,64, No. 4, 267–275 (1988).
V. S. Kuul', O. B. Samoilov, and A. A. Fal'kov, “Study of first-loop depressurization accidents in the AST-500,” in: Abstracts of Proceedings of Seminar “Heat Physics-90” [in Russian], Obninsk (1990), pp. 64–65.
N. S. Al'ferov, A. S. Babykin, B. F. Balunov, et al., “Circulation characteristics of natural-circulation loop of large-scale model of low-boiling reactor,” At. Énerg.,58, No. 3, 159–162 (1985).
A. S. Babykin, B. F. Balunov, T. S. Zhivitskaya, et al., “Pulsation characteristics of natural-circulation loop of large-scale model of low-boiling reactor,” At. Énerg.,58, No. 4, 237–241 (1985).
A. S. Babykin, B. F. Balunov, V. V. Vakhrushev, et al., “Intensity of gas dissolution in water underheated to saturation temperature,” At. Énerg.,64, No. 6, 407–410 (1988).
A. S. Babykin, B. F. Balunov, V. V. Vakhrushev, et al., “Pulsation characteristics of two-fuel-assembly boiling-water reactor,” At. Énerg.,69, No. 2, 87–92 (1990).
B. F. Balunov, R. A. Rybin, E. L. Smirnov, et al., “Study of characteristics of natural-circulation loop of boiling-water reactor with reduction of water level in loop,” Voprosy At. Nauki Tekh., Ser. Fiz. Tekh. Yad. Reakt., No., 3(16), 26–36 (1981).
S. B. Alekseev, B. F. Balunov, Yu. N. Ilyukhin, and S. V. Svetlov, “Critical power of heat-releasing assemblies of water-moderated-water-cooled reactors in emergency situations with cessation of coolant circulation,” in: Abstracts of Proceedings of Seminar “Heat Physics-90” [in Russian], Obninsk (1990), pp. 185-186.
Additional information
I. I. Polzunov Central Scientific-Research and Design Boiler and Turbine Institute. Special Design Office of Mechanical Engineering. Translated from Atomnaya Énergiya, Vol. 73, No. 1, pp. 37–44, July, 1992.
Rights and permissions
About this article
Cite this article
Babykin, A.S., Balunov, B.F., Zhivitskaya, T.S. et al. Experimental demonstration of AST-500 safety with large-scale model of reactor. At Energy 73, 578–584 (1992). https://doi.org/10.1007/BF00749530
Received:
Issue Date:
DOI: https://doi.org/10.1007/BF00749530