Computational Analysis of the initial stage of the accident at the Chernobyl' atomic power plant

Author:

Abagyan A. A.,Arshavskii I. M.,Dmitriev V. M.,Kroshilin A. E.,Krayushkin A. V.,Khalimonchuk V. A.

Publisher

Springer Science and Business Media LLC

Subject

Nuclear Energy and Engineering,General Engineering,Nuclear Energy and Engineering

Reference6 articles.

1. V. M. Dmitriev, ?Mathematical model of a power-generating unit with an RBMK-1000 reactor for analysis of the dynamics of transients during operation of a nuclear power plant,? Vopr. At. Nauki i Tekh., Ser. Fiz. Tekh. Yad. Reaktorov, No. 1, 3?8 (1986).

2. I. M. Arshavskii, F. F. Voskresenskii, V. M. Dmitriev, et al., ?Comparative analysis of computational and experimental results of a study of dynamic operating conditions of power-generating units with an RBMK reactor,? Vopr. At. Nauki i Tekh., Ser. Fiz. Tekh. Yad. Reaktorov, No. 1, 318?324 (1986).

3. V. A. Khalimonchuk and A. V. Krayushkin, TREP ? a High-Speed Program for Study of Unsteady States of an RBMK in Three-Dimensional Geometry [in Russian], Preprint No. KIYaI-90-18 of the Institute of Nuclear Physics of the Academy of Sciences of the Ukrainian SSR.

4. G. Wallis, One-Dimensional Two-Phase Flows [Russian translation], Nauka, Moscow (1972).

5. I. M. Arshavskii and A. E. Kroshilin, ?Mathematical models of the hydrodynamics of coolant flow in the coolant circuit of a nuclear power plant with an RBMK-1000,? At. Énerg.,71, No. 4, 287?293 (1991).

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