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Analysis With Different Containment Models for Containment Response of NHR200II Under Loss‐of‐Coolant Accident.

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Title: Analysis With Different Containment Models for Containment Response of NHR200II Under Loss‐of‐Coolant Accident.
Authors: Wang, Yan1,2 (AUTHOR) wangyanfcw@tsinghua.edu.cn, Meng, Yifan1,2 (AUTHOR), Wang, Zixuan1,2 (AUTHOR), Habib, Mohammad Rezwan (AUTHOR) mohabib@wiley.com
Source: Science & Technology of Nuclear Installations. 5/25/2026, Vol. 2026, p1-13. 13p.
Subject Terms: *Thermal hydraulics, *Lumped parameter systems, *Nuclear power plants, *Distributed parameter systems, *Nuclear accidents, *Nuclear reactors
Abstract: In the design of nuclear power plant systems, the thermal–hydraulic response in the containment during a loss‐of‐coolant accident (LOCA) plays a crucial role. In this study, the advanced small modular reactor NHR200‐II is selected as the research object. The transient responses of the containment during a typical small break LOCA (SBLOCA) with different containment models are modeled and compared, including both the lumped parameter approach with a single volume and the distributed parameter approach with subdivided volumes. The analysis results revealed that the containment pressure responses—a key thermal–hydraulic parameter during SBLOCA transients in the NHR200‐II design—show only minor differences when modeled using the two approaches. These findings indicate that the lumped parameter model can be sufficient to satisfy the requirements for predicting containment pressure responses in the NHR200‐II design. However, further details of thermal–hydraulic phenomena and processes can be achieved through the distributed containment model, such as temperature distribution and fluid velocity within the containment. Notably, it was observed that heat transfer between the vapor and containment shell is a significant heat removal mechanism during the SBLOCA transients in the NHR200‐II. This finding emphasizes the importance of considering heat transfer through the containment shell in future analyses of containment response. [ABSTRACT FROM AUTHOR]
Database: Energy & Power Source
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Header DbId: enr
DbLabel: Energy & Power Source
An: 194010443
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  Label: Title
  Group: Ti
  Data: Analysis With Different Containment Models for Containment Response of NHR200II Under Loss‐of‐Coolant Accident.
– Name: Author
  Label: Authors
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  Data: <searchLink fieldCode="AR" term="%22Wang%2C+Yan%22">Wang, Yan</searchLink><relatesTo>1,2</relatesTo> (AUTHOR)<i> wangyanfcw@tsinghua.edu.cn</i><br /><searchLink fieldCode="AR" term="%22Meng%2C+Yifan%22">Meng, Yifan</searchLink><relatesTo>1,2</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Wang%2C+Zixuan%22">Wang, Zixuan</searchLink><relatesTo>1,2</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Habib%2C+Mohammad+Rezwan%22">Habib, Mohammad Rezwan</searchLink> (AUTHOR)<i> mohabib@wiley.com</i>
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  Data: <searchLink fieldCode="JN" term="%22Science+%26+Technology+of+Nuclear+Installations%22">Science & Technology of Nuclear Installations</searchLink>. 5/25/2026, Vol. 2026, p1-13. 13p.
– Name: Subject
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  Group: Su
  Data: *<searchLink fieldCode="DE" term="%22Thermal+hydraulics%22">Thermal hydraulics</searchLink><br />*<searchLink fieldCode="DE" term="%22Lumped+parameter+systems%22">Lumped parameter systems</searchLink><br />*<searchLink fieldCode="DE" term="%22Nuclear+power+plants%22">Nuclear power plants</searchLink><br />*<searchLink fieldCode="DE" term="%22Distributed+parameter+systems%22">Distributed parameter systems</searchLink><br />*<searchLink fieldCode="DE" term="%22Nuclear+accidents%22">Nuclear accidents</searchLink><br />*<searchLink fieldCode="DE" term="%22Nuclear+reactors%22">Nuclear reactors</searchLink>
– Name: Abstract
  Label: Abstract
  Group: Ab
  Data: In the design of nuclear power plant systems, the thermal–hydraulic response in the containment during a loss‐of‐coolant accident (LOCA) plays a crucial role. In this study, the advanced small modular reactor NHR200‐II is selected as the research object. The transient responses of the containment during a typical small break LOCA (SBLOCA) with different containment models are modeled and compared, including both the lumped parameter approach with a single volume and the distributed parameter approach with subdivided volumes. The analysis results revealed that the containment pressure responses—a key thermal–hydraulic parameter during SBLOCA transients in the NHR200‐II design—show only minor differences when modeled using the two approaches. These findings indicate that the lumped parameter model can be sufficient to satisfy the requirements for predicting containment pressure responses in the NHR200‐II design. However, further details of thermal–hydraulic phenomena and processes can be achieved through the distributed containment model, such as temperature distribution and fluid velocity within the containment. Notably, it was observed that heat transfer between the vapor and containment shell is a significant heat removal mechanism during the SBLOCA transients in the NHR200‐II. This finding emphasizes the importance of considering heat transfer through the containment shell in future analyses of containment response. [ABSTRACT FROM AUTHOR]
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RecordInfo BibRecord:
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      – Type: doi
        Value: 10.1155/stni/9255832
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      – Code: eng
        Text: English
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      Pagination:
        PageCount: 13
        StartPage: 1
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      – SubjectFull: Thermal hydraulics
        Type: general
      – SubjectFull: Lumped parameter systems
        Type: general
      – SubjectFull: Nuclear power plants
        Type: general
      – SubjectFull: Distributed parameter systems
        Type: general
      – SubjectFull: Nuclear accidents
        Type: general
      – SubjectFull: Nuclear reactors
        Type: general
    Titles:
      – TitleFull: Analysis With Different Containment Models for Containment Response of NHR200II Under Loss‐of‐Coolant Accident.
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            NameFull: Wang, Yan
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            NameFull: Meng, Yifan
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            NameFull: Wang, Zixuan
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            – D: 25
              M: 05
              Text: 5/25/2026
              Type: published
              Y: 2026
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              Value: 2026
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            – TitleFull: Science & Technology of Nuclear Installations
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