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Transient Analysis Framework for Heat Pipe Reactors Based on the MOOSE and Its Validation with the KRUSTY Reactor.

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Title: Transient Analysis Framework for Heat Pipe Reactors Based on the MOOSE and Its Validation with the KRUSTY Reactor.
Authors: Xu, Honghui1,2,3 (AUTHOR), Zhang, Naiwen1,2,3 (AUTHOR), Fan, Yuhan1,2,3 (AUTHOR), Ma, Xinran1,2,3,4 (AUTHOR), Zeng, Minghui1,2,4 (AUTHOR), Yan, Rui1,2,3 (AUTHOR), Liu, Yafen1,2,3 (AUTHOR)
Source: Energies (19961073). Apr2026, Vol. 19 Issue 8, p1815. 21p.
Subject Terms: *Transient analysis, *Heat transfer, *Computer simulation, *Nuclear energy safety measures, *Research reactors, *Nuclear reactors
Abstract: Heat pipe cooled reactors rely on heat pipes for passive heat transfer and exhibit high reliability and compactness. Therefore, they are considered candidate nuclear reactor systems for future deep space exploration missions. To enable a deeper investigation of heat pipe reactor systems, particularly the transient response characteristics of the core, a transient coupled analysis framework is developed based on the multi-physics coupling code MOOSE. This framework includes the core heat transfer module, point kinetics module, heat pipe module, and Stirling engine module. A novel strategy that allows two distinct heat pipe models to be simultaneously invoked within a single simulation in MOOSE is developed. All modules are developed within the MOOSE framework and do not rely on any external programs. The heat pipe module is validated using experimental data from heat pipe startup and operation tests within the maximum relative error of only 0.45%. The entire coupled framework is validated against the KRUSTY operational experiments and is compared with other multi-physics models, demonstrating higher accuracy within the maximum relative error of only 13.7% in core load variation conditions. Meanwhile, transient coupled analyses of the KRUSTY reactor are performed to evaluate its safety performance under accident conditions. In the hypothetical positive reactivity step insertion accident and heat pipe failure accidents, the KRUSTY core exhibits excellent safety performance. And the mechanism of heat pipe power redistribution following heat pipe failure is examined in detail. [ABSTRACT FROM AUTHOR]
Database: Energy & Power Source
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Header DbId: enr
DbLabel: Energy & Power Source
An: 193438155
AccessLevel: 6
PubType: Academic Journal
PubTypeId: academicJournal
PreciseRelevancyScore: 0
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  Label: Title
  Group: Ti
  Data: Transient Analysis Framework for Heat Pipe Reactors Based on the MOOSE and Its Validation with the KRUSTY Reactor.
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  Label: Authors
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  Data: <searchLink fieldCode="AR" term="%22Xu%2C+Honghui%22">Xu, Honghui</searchLink><relatesTo>1,2,3</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Zhang%2C+Naiwen%22">Zhang, Naiwen</searchLink><relatesTo>1,2,3</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Fan%2C+Yuhan%22">Fan, Yuhan</searchLink><relatesTo>1,2,3</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Ma%2C+Xinran%22">Ma, Xinran</searchLink><relatesTo>1,2,3,4</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Zeng%2C+Minghui%22">Zeng, Minghui</searchLink><relatesTo>1,2,4</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Yan%2C+Rui%22">Yan, Rui</searchLink><relatesTo>1,2,3</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Liu%2C+Yafen%22">Liu, Yafen</searchLink><relatesTo>1,2,3</relatesTo> (AUTHOR)
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  Data: <searchLink fieldCode="JN" term="%22Energies+%2819961073%29%22">Energies (19961073)</searchLink>. Apr2026, Vol. 19 Issue 8, p1815. 21p.
– Name: Subject
  Label: Subject Terms
  Group: Su
  Data: *<searchLink fieldCode="DE" term="%22Transient+analysis%22">Transient analysis</searchLink><br />*<searchLink fieldCode="DE" term="%22Heat+transfer%22">Heat transfer</searchLink><br />*<searchLink fieldCode="DE" term="%22Computer+simulation%22">Computer simulation</searchLink><br />*<searchLink fieldCode="DE" term="%22Nuclear+energy+safety+measures%22">Nuclear energy safety measures</searchLink><br />*<searchLink fieldCode="DE" term="%22Research+reactors%22">Research reactors</searchLink><br />*<searchLink fieldCode="DE" term="%22Nuclear+reactors%22">Nuclear reactors</searchLink>
– Name: Abstract
  Label: Abstract
  Group: Ab
  Data: Heat pipe cooled reactors rely on heat pipes for passive heat transfer and exhibit high reliability and compactness. Therefore, they are considered candidate nuclear reactor systems for future deep space exploration missions. To enable a deeper investigation of heat pipe reactor systems, particularly the transient response characteristics of the core, a transient coupled analysis framework is developed based on the multi-physics coupling code MOOSE. This framework includes the core heat transfer module, point kinetics module, heat pipe module, and Stirling engine module. A novel strategy that allows two distinct heat pipe models to be simultaneously invoked within a single simulation in MOOSE is developed. All modules are developed within the MOOSE framework and do not rely on any external programs. The heat pipe module is validated using experimental data from heat pipe startup and operation tests within the maximum relative error of only 0.45%. The entire coupled framework is validated against the KRUSTY operational experiments and is compared with other multi-physics models, demonstrating higher accuracy within the maximum relative error of only 13.7% in core load variation conditions. Meanwhile, transient coupled analyses of the KRUSTY reactor are performed to evaluate its safety performance under accident conditions. In the hypothetical positive reactivity step insertion accident and heat pipe failure accidents, the KRUSTY core exhibits excellent safety performance. And the mechanism of heat pipe power redistribution following heat pipe failure is examined in detail. [ABSTRACT FROM AUTHOR]
PLink https://search.ebscohost.com/login.aspx?direct=true&site=eds-live&db=enr&AN=193438155
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        Value: 10.3390/en19081815
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      – Code: eng
        Text: English
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        PageCount: 21
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        Type: general
      – SubjectFull: Heat transfer
        Type: general
      – SubjectFull: Computer simulation
        Type: general
      – SubjectFull: Nuclear energy safety measures
        Type: general
      – SubjectFull: Research reactors
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      – SubjectFull: Nuclear reactors
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      – TitleFull: Transient Analysis Framework for Heat Pipe Reactors Based on the MOOSE and Its Validation with the KRUSTY Reactor.
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            NameFull: Xu, Honghui
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            NameFull: Zhang, Naiwen
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            NameFull: Fan, Yuhan
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            NameFull: Zeng, Minghui
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            – D: 15
              M: 04
              Text: Apr2026
              Type: published
              Y: 2026
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              Value: 19
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              Value: 8
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            – TitleFull: Energies (19961073)
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