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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]
Copyright of Nuclear Engineering & Design is the property of Elsevier B.V. and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
Database: Engineering Source
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DbLabel: Engineering Source
An: 189883396
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PubTypeId: academicJournal
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Items – Name: Title
  Label: Title
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  Data: Modeling and experimental study of pressurization and depressurization processes of control rod hydraulic drive system.
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  Data: <searchLink fieldCode="AR" term="%22Yang%2C+Linqing%22">Yang, Linqing</searchLink><relatesTo>1</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Qin%2C+Benke%22">Qin, Benke</searchLink><relatesTo>1</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Li%2C+Yun%22">Li, Yun</searchLink><relatesTo>1</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Li%2C+Yanlin%22">Li, Yanlin</searchLink><relatesTo>1</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Bo%2C+Hanliang%22">Bo, Hanliang</searchLink><relatesTo>1</relatesTo> (AUTHOR)<i> bohl@tsinghua.edu.cn</i>
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  Data: <searchLink fieldCode="JN" term="%22Nuclear+Engineering+%26+Design%22">Nuclear Engineering & Design</searchLink>. Jan2026:Part A, Vol. 446, pN.PAG-N.PAG. 1p.
– Name: Subject
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  Data: <searchLink fieldCode="DE" term="%22Nuclear+reactors%22">Nuclear reactors</searchLink><br /><searchLink fieldCode="DE" term="%22System+safety%22">System safety</searchLink><br /><searchLink fieldCode="DE" term="%22Compression+loads%22">Compression loads</searchLink><br /><searchLink fieldCode="DE" term="%22Unsteady+flow+%28Aerodynamics%29%22">Unsteady flow (Aerodynamics)</searchLink><br /><searchLink fieldCode="DE" term="%22Decompression+%28Physiology%29%22">Decompression (Physiology)</searchLink><br /><searchLink fieldCode="DE" term="%22Model+validation%22">Model validation</searchLink><br /><searchLink fieldCode="DE" term="%22Dynamic+pressure%22">Dynamic pressure</searchLink><br /><searchLink fieldCode="DE" term="%22Hydraulic+drive%22">Hydraulic drive</searchLink>
– Name: Abstract
  Label: Abstract
  Group: Ab
  Data: • 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]
– Name: AbstractSuppliedCopyright
  Label:
  Group: Ab
  Data: <i>Copyright of Nuclear Engineering & Design is the property of Elsevier B.V. and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract.</i> (Copyright applies to all Abstracts.)
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RecordInfo BibRecord:
  BibEntity:
    Identifiers:
      – Type: doi
        Value: 10.1016/j.nucengdes.2025.114560
    Languages:
      – Code: eng
        Text: English
    PhysicalDescription:
      Pagination:
        PageCount: 1
        StartPage: N.PAG
    Subjects:
      – SubjectFull: Nuclear reactors
        Type: general
      – SubjectFull: System safety
        Type: general
      – SubjectFull: Compression loads
        Type: general
      – SubjectFull: Unsteady flow (Aerodynamics)
        Type: general
      – SubjectFull: Decompression (Physiology)
        Type: general
      – SubjectFull: Model validation
        Type: general
      – SubjectFull: Dynamic pressure
        Type: general
      – SubjectFull: Hydraulic drive
        Type: general
    Titles:
      – TitleFull: Modeling and experimental study of pressurization and depressurization processes of control rod hydraulic drive system.
        Type: main
  BibRelationships:
    HasContributorRelationships:
      – PersonEntity:
          Name:
            NameFull: Yang, Linqing
      – PersonEntity:
          Name:
            NameFull: Qin, Benke
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            NameFull: Li, Yun
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            NameFull: Li, Yanlin
      – PersonEntity:
          Name:
            NameFull: Bo, Hanliang
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          Dates:
            – D: 01
              M: 01
              Text: Jan2026:Part A
              Type: published
              Y: 2026
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              Value: 00295493
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            – Type: volume
              Value: 446
          Titles:
            – TitleFull: Nuclear Engineering & Design
              Type: main
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