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Thermal‐Hydraulic Characterization Preliminary Analysis of Pool‐Type Natural Circulation With Liquid Lead.

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Title: Thermal‐Hydraulic Characterization Preliminary Analysis of Pool‐Type Natural Circulation With Liquid Lead.
Authors: Liu, Yang1 (AUTHOR), Wang, Xiangyang2,3 (AUTHOR), Zhang, Lu2 (AUTHOR) zhang_lu@lzu.edu.cn, Li, Hu (AUTHOR) lihu860628@126.com
Source: International Journal of Energy Research. 3/25/2026, Vol. 2026, p1-13. 13p.
Subject Terms: *Fast reactors, *Liquid metals, *Buoyancy-driven flow, *Nuclear reactors, *Natural heat convection, *Empirical research, *Simulation methods & models, *Thermal hydraulics
Abstract: Lead‐cooled fast reactors are an important potential reactor type in the fourth‐generation nuclear energy system. And the clarity of the thermal‐hydraulic characteristics of pool‐type natural circulation is crucial for the design of lead‐based fast reactors. This study focuses on liquid lead and conducts experimental research on the characteristics of pool‐type natural circulation. Based on the pool‐type structure, megawatt‐scale natural circulation tests were carried out, achieving stable natural circulation at a final input power of 503 kW, which demonstrates the feasibility of the natural circulation design in a liquid lead pool. Meanwhile, experimental modeling using the redeveloped system code RELAP5/MOD4.0 was performed, and the verification analysis demonstrates that the redeveloped code can accurately simulate the experiment. The comparison shows that the experimental results and calculations exhibit the same trend, and the errors in core inlet temperature, outlet temperature, and inlet pressure are 2.5%, 2.2%, and 5.8%, respectively. This study experimentally verified the feasibility of the pool‐type natural circulation design and further redeveloped a system analysis code suitable for numerical simulation. The verification with experiments also demonstrated the accuracy of the new code for the simulation of lead‐cooled fast reactors. Considering the scarcity of research reports on natural circulation in pure liquid lead pools, the research outcomes can provide support for the design of pool‐type natural circulation reactors using liquid lead. [ABSTRACT FROM AUTHOR]
Database: Energy & Power Source
FullText Text:
  Availability: 0
Header DbId: enr
DbLabel: Energy & Power Source
An: 192506201
AccessLevel: 6
PubType: Academic Journal
PubTypeId: academicJournal
PreciseRelevancyScore: 0
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Items – Name: Title
  Label: Title
  Group: Ti
  Data: Thermal‐Hydraulic Characterization Preliminary Analysis of Pool‐Type Natural Circulation With Liquid Lead.
– Name: Author
  Label: Authors
  Group: Au
  Data: <searchLink fieldCode="AR" term="%22Liu%2C+Yang%22">Liu, Yang</searchLink><relatesTo>1</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Wang%2C+Xiangyang%22">Wang, Xiangyang</searchLink><relatesTo>2,3</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Zhang%2C+Lu%22">Zhang, Lu</searchLink><relatesTo>2</relatesTo> (AUTHOR)<i> zhang_lu@lzu.edu.cn</i><br /><searchLink fieldCode="AR" term="%22Li%2C+Hu%22">Li, Hu</searchLink> (AUTHOR)<i> lihu860628@126.com</i>
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  Label: Source
  Group: Src
  Data: <searchLink fieldCode="JN" term="%22International+Journal+of+Energy+Research%22">International Journal of Energy Research</searchLink>. 3/25/2026, Vol. 2026, p1-13. 13p.
– Name: Subject
  Label: Subject Terms
  Group: Su
  Data: *<searchLink fieldCode="DE" term="%22Fast+reactors%22">Fast reactors</searchLink><br />*<searchLink fieldCode="DE" term="%22Liquid+metals%22">Liquid metals</searchLink><br />*<searchLink fieldCode="DE" term="%22Buoyancy-driven+flow%22">Buoyancy-driven flow</searchLink><br />*<searchLink fieldCode="DE" term="%22Nuclear+reactors%22">Nuclear reactors</searchLink><br />*<searchLink fieldCode="DE" term="%22Natural+heat+convection%22">Natural heat convection</searchLink><br />*<searchLink fieldCode="DE" term="%22Empirical+research%22">Empirical research</searchLink><br />*<searchLink fieldCode="DE" term="%22Simulation+methods+%26+models%22">Simulation methods & models</searchLink><br />*<searchLink fieldCode="DE" term="%22Thermal+hydraulics%22">Thermal hydraulics</searchLink>
– Name: Abstract
  Label: Abstract
  Group: Ab
  Data: Lead‐cooled fast reactors are an important potential reactor type in the fourth‐generation nuclear energy system. And the clarity of the thermal‐hydraulic characteristics of pool‐type natural circulation is crucial for the design of lead‐based fast reactors. This study focuses on liquid lead and conducts experimental research on the characteristics of pool‐type natural circulation. Based on the pool‐type structure, megawatt‐scale natural circulation tests were carried out, achieving stable natural circulation at a final input power of 503 kW, which demonstrates the feasibility of the natural circulation design in a liquid lead pool. Meanwhile, experimental modeling using the redeveloped system code RELAP5/MOD4.0 was performed, and the verification analysis demonstrates that the redeveloped code can accurately simulate the experiment. The comparison shows that the experimental results and calculations exhibit the same trend, and the errors in core inlet temperature, outlet temperature, and inlet pressure are 2.5%, 2.2%, and 5.8%, respectively. This study experimentally verified the feasibility of the pool‐type natural circulation design and further redeveloped a system analysis code suitable for numerical simulation. The verification with experiments also demonstrated the accuracy of the new code for the simulation of lead‐cooled fast reactors. Considering the scarcity of research reports on natural circulation in pure liquid lead pools, the research outcomes can provide support for the design of pool‐type natural circulation reactors using liquid lead. [ABSTRACT FROM AUTHOR]
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RecordInfo BibRecord:
  BibEntity:
    Identifiers:
      – Type: doi
        Value: 10.1155/er/4886439
    Languages:
      – Code: eng
        Text: English
    PhysicalDescription:
      Pagination:
        PageCount: 13
        StartPage: 1
    Subjects:
      – SubjectFull: Fast reactors
        Type: general
      – SubjectFull: Liquid metals
        Type: general
      – SubjectFull: Buoyancy-driven flow
        Type: general
      – SubjectFull: Nuclear reactors
        Type: general
      – SubjectFull: Natural heat convection
        Type: general
      – SubjectFull: Empirical research
        Type: general
      – SubjectFull: Simulation methods & models
        Type: general
      – SubjectFull: Thermal hydraulics
        Type: general
    Titles:
      – TitleFull: Thermal‐Hydraulic Characterization Preliminary Analysis of Pool‐Type Natural Circulation With Liquid Lead.
        Type: main
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            NameFull: Liu, Yang
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            NameFull: Wang, Xiangyang
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            NameFull: Zhang, Lu
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            NameFull: Li, Hu
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            – D: 25
              M: 03
              Text: 3/25/2026
              Type: published
              Y: 2026
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            – Type: issn-print
              Value: 0363907X
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              Value: 2026
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            – TitleFull: International Journal of Energy Research
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