Literature Cited
U. Schumann, Nucl. Eng. Design,73, 303 (1982).
Z. Gavelka, M. Sukhanek, and O. Kodim, “An experimental study of the effects of shock waves on a model reactor pit in simulating an accident involving coolant loss,” Paper at the Comecon Seminar Teplofizika-82 [in Russian], Karlovy Vary (1982).
U. Schumann, Nucl. Eng. Design, 69, 313 (1982).
F. Chang et al.,ibid.,70, 335 (1972).
S. Benedek, “Comparison of calculations from the BRUKh-D and TECh'-12 models on the consequences of failure of a large pipeline in the VVÉR-440 reactor,” Paper at the Comecon Seminar Teplofizika-78 [in Russian], Budapest (1978).
A. M. Bukrinskii and R. L. Fuks, Teploperedacha, No. 7, 77 (1977).
N. Kolev and L. Sabotinov, Kernenergie,23, No. 6 230 (1980).
S. Fischer et al., RELAP4/MOD6: A Computer Program for Transient Thermal-Hydraulic Analysis of Nuclear Reactors and Related Systems, CDAP TR 003, Idaho EG and G (1978).
V. Adamik and A. Tkach, “Computational models for pressure-wave propagation in the first circuit of a VVÉR-440 reactor,” Paper at the Comecon Seminar Teplofizika-82 [in Russian], Karlovy Vary (1982).
A. M. Bukrinskii, Emergency Transients in Nuclear Power Stations Containing VVÉR Reactors [in Russian], Énergoizdat, Moscow (1982).
Additional information
Nuclear Research and Nuclear Power Institute, Bulgarian Academy of Sciences, Sofia. Translated from Atomnaya Énergiya, Vol. 56, No. 4, pp. 234–235, April, 1984.
Rights and permissions
About this article
Cite this article
Boyadzhiev, A.I., Stefanova, S.I. Shock loads on units within the containment in the VVÉR-1000 in the initial stage of an emergency involving failure in the main circulation pipeline. At Energy 56, 264–267 (1984). https://doi.org/10.1007/BF01124194
Received:
Issue Date:
DOI: https://doi.org/10.1007/BF01124194