Calculation and experimental substantiation of thermal-hydraulic characteristics for the emergency cooldown system of BN-800 reactor

IF 0.4 4区 工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY Atomic Energy Pub Date : 2025-03-03 DOI:10.1007/s10512-025-01182-3
V. V. Pakholkov, S. A. Rogozhkin, S. F. Shepelev
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Abstract

The present paper considers thermal-hydraulic tests of an emergency cooldown system for the BN-800 reactor with forced circulation of sodium in the primary and secondary circuits. The operating range of changes in the flow rate of coolants in the system under various operating modes is determined. Heat transfer in the air heat exchangers of BN-600 and BN-800 reactors is examined. The established Nusselt number dependence is in satisfactory agreement with the RD 24.035.05-89 methodological guidelines. A simple relationship has been obtained using the results of tests and calculations for assessing the capacity of air heat exchangers. The possibility of increasing their capacity by 26% compared to the design value is demonstrated. The significance of the thermosiphon effect on the temperature state of fittings in the emergency cooldown system is demonstrated. The experimental models have revealed the effect of pipeline inclination on the intensity of heat transfer.

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来源期刊
Atomic Energy
Atomic Energy 工程技术-核科学技术
CiteScore
1.00
自引率
20.00%
发文量
100
审稿时长
4-8 weeks
期刊介绍: Atomic Energy publishes papers and review articles dealing with the latest developments in the peaceful uses of atomic energy. Topics include nuclear chemistry and physics, plasma physics, accelerator characteristics, reactor economics and engineering, applications of isotopes, and radiation monitoring and safety.
期刊最新文献
Critical factors of an integrated approach to the economics of small modular reactors Fire protection system for sodium equipment rooms of BN reactors: operating experience and development trends Neutron codes for calculating advanced reactor plants with a liquid metal coolant Calculation and experimental substantiation of thermal-hydraulic characteristics for the emergency cooldown system of BN-800 reactor Innovative technologies for immobilizing the sodium primary coolant of fast neutron reactors and processing liquid radioactive waste generated during reactor operation
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