NUCLEAR TECHNIQUES, Volume. 48, Issue 7, 070027(2025)

Application of a one-dimensional solidification model in safety analysis of generation IV reactors using high melting point coolants

Maolong LIU1、*, Chen ZENG2,3, Cong SHEN3, Yalun YAN4, and Yulong MAO4
Author Affiliations
  • 1Fudan University, Shanghai 200433, China
  • 2(Shanghai Nuclear Engineering Research & Design Institute Co., Ltd., Shanghai 200233, China) 3(Shanghai Jiao Tong University, Shanghai 200240, China)
  • 3China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen 518000, China
  • 4[in Chinese]
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    Figures & Tables(8)
    Framework diagram of the one-dimensional solidification mechanism model (color online)
    Schematic diagram of the solidification microelement inside the tube (color online)
    Solidification diagram inside the tube (color online)
    Distribution of dimensionless instantaneous solidified layer thickness for Case 1 penetration pipe at the moment before complete blockage of the pipe (color online) (a) Mesh sensitivity analysis, (b) Time step sensitivity analysis
    Distribution of dimensionless solidified layer thickness along the penetration pipe at the moment before complete blockage of the pipe (a) and the comparison of experimental and simulated results (b) (color online)
    Variation of mass flow rate of the primary loop before and after shutdown (color online)
    Temperature evolution (a) and mass flow rate evolution (b) at multiple locations of the reactor after shutdown (color online)
    Evolution of the dimensionless thickness of the solidified layer (δ*) in LWHX tube side at the inlet and outlet (a) and the distribution of δ*in the LWHX tube side at the moment just before the failure time (b)
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    Maolong LIU, Chen ZENG, Cong SHEN, Yalun YAN, Yulong MAO. Application of a one-dimensional solidification model in safety analysis of generation IV reactors using high melting point coolants[J]. NUCLEAR TECHNIQUES, 2025, 48(7): 070027

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    Paper Information

    Category: Special Issue on The First Academic Annual Conference of the Research Reactor and Innovative Reactor Association of Chinese Nuclear Society and Advanced Nuclear Power System Reactor Engineering

    Received: Feb. 25, 2025

    Accepted: --

    Published Online: Sep. 15, 2025

    The Author Email: Maolong LIU (maolongliu@fudan.edu.cn)

    DOI:10.11889/j.0253-3219.2025.hjs.48.250082

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