• NUCLEAR TECHNIQUES
  • Vol. 47, Issue 1, 010604 (2024)
Jingxiang MA, Shichang DONG, and Shengjie GONG*
Author Affiliations
  • Shanghai Jiao Tong University, Shanghai 200240, China
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    DOI: 10.11889/j.0253-3219.2024.hjs.47.010604 Cite this Article
    Jingxiang MA, Shichang DONG, Shengjie GONG. Numerical simulation of thermal stratification phenomenon in stagnant branch pipe of pressurized water reactors[J]. NUCLEAR TECHNIQUES, 2024, 47(1): 010604 Copy Citation Text show less

    Abstract

    Background

    In thermal pipelines of nuclear power systems, thermal stratification is a common phenomenon that can cause stress concentration and deformation of pipeline structures, thereby leading to safety hazards. A stagnant branch pipe is connected to the main coolant pipe, and a large temperature difference exists between the fluid in the pipe and the coolant in the main pipe of the primary circuit. Due to factors such as turbulent flow penetration and valve leakage, thermal stratification is prone to occur in the branch pipe.

    Purpose

    This study aims to analyze the temperature change characteristics and flow characteristics of thermal stratification in stagnant branch pipes and provide a theoretical basis for subsequent experimental research and stress analysis.

    Methods

    Firstly, a stagnant branch pipe model was established, and numerical simulation of thermal stratification phenomenon in stagnant branch pipes was conducted using FLUENT 2022 to analyze the temperature variation characteristics of the pipe wall and the distribution characteristics of the flow field inside the pipe. Then, the SST k-ω model was used to perform three-dimensional numerical simulation of the thermal stratification of stagnant branch pipes, with a leakage flow rate of 0.062 kg·s-1, leakage temperature of 488.15 K, and leakage pressure of 6 MPa.

    Results

    Thermal stratification is prone to occur in horizontal pipe sections. Without insulation measures and a large pipe diameter, thermal stratification can be exacerbated, while the curved section can effectively reduce the temperature difference of the cross-section. A backflow phenomenon occurs in the horizontal section of the stagnant branch pipe, while the structure of the large and small end pipe sections causes secondary backflow in the flow field inside the pipe. The backflow phenomenon is not conducive to the mixing of cold and hot fluids in the pipe; consequently, the influence time of thermal stratification is longer.

    Conclusions

    A significant difference in the thermal stratification phenomenon exists between the stagnant branch pipe and equal cross-section pipes.

    Jingxiang MA, Shichang DONG, Shengjie GONG. Numerical simulation of thermal stratification phenomenon in stagnant branch pipe of pressurized water reactors[J]. NUCLEAR TECHNIQUES, 2024, 47(1): 010604
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