For the possible operation of power units with the RBMK-1000 reactor during the period of the formation of a graphite stack, NIKIET performed a series of experiments to recreate the force action of the graphite stack on the sealed vessel of the reactor, represented by the KZh metal structure. The experiments justified the joint movement of the graphite stack and 50 mm metal structure with the assumption of up to 5% local plastic deformations of the metal structure at the contact with the graphite stack, which was beyond the limits of the strength calculations valid at the time of works. As a part of the performed study, the behavior of graphite blocks during their destruction under interaction with the metal barrier was determined. The experiments, which revealed the significant conservatism of previous calculations, showed that graphite blocks can be destroyed under interaction with the metal structure without damaging the safety barrier.
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A. V. Slobodchikov, V. L. Reshetin, A. P. Mikhal’chenko, et al., “Justification of the operation safety for the RBMK power unit during the power interaction of the KZh steel structure and the graphite stack,” in: Scientific and Technical Annual Report of NIKIET (2018), pp. 62–65.
A. V. Slobodchikov, A. N. Biryukov, A. V. Zhmakin, et al., “Experimental study of the force interaction between the elements of the KZh steel structure and the graphite stack of the RBMK-1000 reactor plant during their contact,” in: Scientific and Technical Annual Report of NIKIET (2021), pp. 211–213.
Software Certificate No. 486, Abaqus Software Package for Solving the Problems of Dynamics and Strength, Dec. 19, 2019, NTTs YaRB, Moscow (2019).
STO 95 12048-2019, Ensuring the Iintegrity of the Reactor Vessel, Pipelines, and Intra-Vessel Devices of a Nuclear Power Plant with a Lead Coolant. Equipment, Pipelines and Intra-Vessel Devices. Verification Strength Calculation, Rosatom State Corporation, Moscow (2019).
STO 95 12052-2019, Ensuring the Integrity of the Reactor Vessel, Pipelines and Intra-Vessel Devices of a Nuclear Power Plant with a Lead Coolant. Reactor Vessel. Strength Calculation, Rosatom State Corporation, Moscow (2019).
GOST R 59115.9-2021, Strength Justification for the Equipment and Pipelines of Nuclear Power Plants. Verification Strength Calculations, RST, Moscow (2022).
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Translated from Atomnaya Énergiya, Vol. 133, No. 5–6, pp. 254–257, November–December, 2022.
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Slobodchikov, A.V., Biryukov, A.N., Rakhmanov, A.P. et al. Calculation and Experimental Study of the Interaction Between a KZh Steel Structure and RBMK-1000 Graphite Stack. At Energy 133, 264–268 (2023). https://doi.org/10.1007/s10512-023-01006-2
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DOI: https://doi.org/10.1007/s10512-023-01006-2