NUCLEAR TECHNIQUES, Volume. 47, Issue 1, 010604(2024)

Numerical simulation of thermal stratification phenomenon in stagnant branch pipe of pressurized water reactors

Jingxiang MA, Shichang DONG, and Shengjie GONG*
Author Affiliations
  • Shanghai Jiao Tong University, Shanghai 200240, China
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    References(19)

    [2] QIN Jie. CFD research on normally stagnant non-isolable branch lines attached to RCS loop piping[J]. Nuclear Power Engineering, 32, 149-151, 161(2011).

    [6] NRC U. Thermal stresses in piping connected to reactor coolant systems[R]. NRC Bulletin No.8, 88(1988).

    [7] NRC U[S]. Pressurizer surge line thermal stratification(1988).

    [10] HE Bin. Research on the flow and heat transfer of thermal stratification in an injection pipeline of steam generator[D](2016).

    [11] CAO Qiong, LU Daogang, ZHANG Yuhao et al. Numerical study on thermal stratification of AP1000 ADS-4 A-pipline[C], 15-22(2017).

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    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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    Paper Information

    Category: Research Articles

    Received: Jun. 13, 2023

    Accepted: --

    Published Online: Mar. 7, 2024

    The Author Email: GONG Shengjie (龚圣捷)

    DOI:10.11889/j.0253-3219.2024.hjs.47.010604

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