Integrity Assessment of RBMK Physical Safety Barriers during Prolonged Station Power-Unit De-Energization

Two successive stages of the control of a beyond-design basis accident with de-energization of an RBMK reactor together with multiple equipment failures are analyzed: depressurization of the circulation loop and restoration of reactor cooldown with cold water as the reactor subsequently warms up. Th...

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Bibliographic Details
Published in:Atomic energy (New York, N.Y.) N.Y.), 2020-09, Vol.128 (5), p.265-270
Main Authors: Bubnova, T. A., Kaplienko, A. V., Nikitin, Yu. M., Slobodchikov, A. V., Umyarov, R. M.
Format: Article
Language:English
Subjects:
Cold water
Control equipment
Deformation analysis
Energy industry
Failure analysis
Hadrons
Heavy Ions
Integrity
Nuclear Chemistry
Nuclear Energy
Nuclear engineering
Nuclear Physics
Nuclear power plants
Nuclear safety
Physics
Physics and Astronomy
Pressure reduction
Pressure surges
RBMK
Reactors
Restoration
Safety barriers
Tubes
Water circulation
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Summary:Two successive stages of the control of a beyond-design basis accident with de-energization of an RBMK reactor together with multiple equipment failures are analyzed: depressurization of the circulation loop and restoration of reactor cooldown with cold water as the reactor subsequently warms up. The factors affecting the pressure surge in the circulation loop on restoration of reactor cooling as the reactor heats up are examined. It is shown that the sequence of control actions and the employed equipment are effective from the standpoint of the possibility of overpressurization of the channel tubes and the reactor space. The state of the channel tubes and the reactor space in the presence of arising deformation loads was analyzed using an experimentally determined criterion for the acceptability (integrity) of a channel tube.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-020-00686-4