Abstract
A full-scale thermohydraulic stand for RBMK safety (FSS RBMK) is under construction at the Energy Scientific-Research Center. The purpose of the stand is to perform local and integrated experiments. The experiments are specially intended for verifying computational codes. They will be accompanied by careful monitoring of all regime parameters, the volume of experimental measurements will be adequate, and the measurements will be documented and stored.
The article gives a brief description of the construction of the stand and the parameter measuring system. A classification of the regimes which can be studied on FSS RBMK (quasistationary, transient, loss-of-coolant regimes) is given. The list of phenomena and processes which are important from the standpoint of the flow of an accident in a real reactor and can be reproduced on the stand is given. A list of planned experiments, the most important of which are indicated, is given.
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REFERENCES
Recommendations for More Detailed Safety Assessment of Operating Power-Generating Units of Nuclear Power Plants with VVER and RBMK reactors (OUOB AS). RB G-12-42-97, Nuclear and Radiation Safety Manual, introduced on September 17, 1997, Moscow (1997).
Standard Content of the Technical Substantiation of the Safety of Nuclear Power Plants (TS TOB AC-85), Rules and Norms in Atomic Energy PN AEG 7-1-001-85, Energoatomizdat, Moscow (1987).
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Translated from Atomnaya Energiya, Vol. 99, No. 2, pp. 95–102, August 2005.
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Brus, N.A., Mironov, Y.V., Afremov, D.A. et al. Basic Problems of Experimental Studies of Accident and Transient Regimes of an RBMK Reactor on an Integrated Thermohydraulic Stand. At Energy 99, 528–535 (2005). https://doi.org/10.1007/s10512-005-0242-2
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DOI: https://doi.org/10.1007/s10512-005-0242-2