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Modeling and experimental study of pressurization and depressurization processes of control rod hydraulic drive system.

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Title: Modeling and experimental study of pressurization and depressurization processes of control rod hydraulic drive system.
Authors: Yang, Linqing1 (AUTHOR), Qin, Benke1 (AUTHOR), Li, Yun1 (AUTHOR), Li, Yanlin1 (AUTHOR), Bo, Hanliang1 (AUTHOR) bohl@tsinghua.edu.cn
Source: Nuclear Engineering & Design. Jan2026:Part A, Vol. 446, pN.PAG-N.PAG. 1p.
Subjects: Nuclear reactors, System safety, Compression loads, Unsteady flow (Aerodynamics), Decompression (Physiology), Model validation, Dynamic pressure, Hydraulic drive
Abstract: • The transient flow characteristics of Control rod hydraulic drive system (CRHDS) greatly affects reactor safety. • The transient flow theoretical model of CRHDS is established. • The mechanism of the pressurization process and depressurization process of CRHDS is revealed. • The variation rule of the transient flow characteristic parameters is analyzed, and the fitting function is established. Control rod hydraulic drive system (CRHDS) is a new built-in drive technology planned for nuclear heating reactors. During normal operation, CRHDS can cause a significant variation in fluid pressure, which could compromise system security. The transient flow model for CRHDS is developed. The full-scale performance experimental rig is constructed to validate the model. Ultimately, the model has been expanded to the variable pump pressure and temperature conditions, and the influence of the characteristic parameters are examined. The results show that the transient flow model for CRHDS reflects the overall slow flow and the local transient flow. With the increasing of pump pressure, the pressurization time decreases gradually, the pressure peak increases gradually, and the depressurization time changes little. With the increasing of fluid temperature, the pressurization time, depressurization time, and pressure peak decrease gradually. This research results serve as the foundation and guidance for the CRHDS operation monitoring and vibration reduction to ensure the system safety. [ABSTRACT FROM AUTHOR]
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Database: Engineering Source
Description
Abstract:• The transient flow characteristics of Control rod hydraulic drive system (CRHDS) greatly affects reactor safety. • The transient flow theoretical model of CRHDS is established. • The mechanism of the pressurization process and depressurization process of CRHDS is revealed. • The variation rule of the transient flow characteristic parameters is analyzed, and the fitting function is established. Control rod hydraulic drive system (CRHDS) is a new built-in drive technology planned for nuclear heating reactors. During normal operation, CRHDS can cause a significant variation in fluid pressure, which could compromise system security. The transient flow model for CRHDS is developed. The full-scale performance experimental rig is constructed to validate the model. Ultimately, the model has been expanded to the variable pump pressure and temperature conditions, and the influence of the characteristic parameters are examined. The results show that the transient flow model for CRHDS reflects the overall slow flow and the local transient flow. With the increasing of pump pressure, the pressurization time decreases gradually, the pressure peak increases gradually, and the depressurization time changes little. With the increasing of fluid temperature, the pressurization time, depressurization time, and pressure peak decrease gradually. This research results serve as the foundation and guidance for the CRHDS operation monitoring and vibration reduction to ensure the system safety. [ABSTRACT FROM AUTHOR]
ISSN:00295493
DOI:10.1016/j.nucengdes.2025.114560