Advance Search
Volume 43 Issue 2
Apr.  2022
Turn off MathJax
Article Contents
Ye Tingpu, Lyu Lulu, Zhang Ge, He Hui, Cheng Cheng. Evaluation of Single-phase and Two-phase Mixing Models for Rod Bundle Channel[J]. Nuclear Power Engineering, 2022, 43(2): 47-52. doi: 10.13832/j.jnpe.2022.02.0047
Citation: Ye Tingpu, Lyu Lulu, Zhang Ge, He Hui, Cheng Cheng. Evaluation of Single-phase and Two-phase Mixing Models for Rod Bundle Channel[J]. Nuclear Power Engineering, 2022, 43(2): 47-52. doi: 10.13832/j.jnpe.2022.02.0047

Evaluation of Single-phase and Two-phase Mixing Models for Rod Bundle Channel

doi: 10.13832/j.jnpe.2022.02.0047
  • Received Date: 2021-02-09
  • Accepted Date: 2021-02-09
  • Rev Recd Date: 2021-05-29
  • Publish Date: 2022-04-02
  • In this study, the subchannel program is used to evaluate the single-phase and two-phase mixing model of the rod bundle channel based on the existing experimental data. The single-phase mixing mainly considers the cross flow and turbulent mixing. The cross flow is determined by the conservation equation and plays a leading role in the flow distribution. The turbulent mixing depends on the mixing coefficient. It is found that the prediction results of Sadatomi model are in good agreement with the experimental results in the study of turbulent mixing. Two-phase mixing is jointly caused by cross flow, turbulent mixing and void drift. Through the comparative analysis of the prediction results of the existing models and the experimental data, it is recommended to use the Hotta model for the void drift in the two-phase mixing, the Sadatomi model for the turbulent mixing coefficient, and the Beus model for the two-phase multiplier. This is a combined model with conservative prediction results, which is conducive to the conservative evaluation of reactor safety.

     

  • loading
  • [1]
    LAHEY R T JR, MOODY F J. The thermal-hydraulics of a boiling water nuclear reactor[M]. 2nd ed. La Grange Park: American Nuclear Society, 1993: 168-184.
    [2]
    PANG B, CHENG X. Proposal of a new type of two-phase interchannel mixing model for application to subchannel analysis of PWR conditions[J]. Annals of Nuclear Energy, 2014, 73: 108-121. doi: 10.1016/j.anucene.2014.06.033
    [3]
    KELLY J E, KAO S P, KAZIMI M S. THERMIT-2: a two-fluid model for light water reactor sub-channel transient analysis: MIT-EL-81-014[R]. USA,Cambridge: MIT, 1981.
    [4]
    ROGERS J T, ROSEHART R G. Mixing by turbulent interchange in fuel bundles, correlations and inferences: ASME 72-HT-53[R]. USA: ASME, 1972
    [5]
    SADATOMI M, KAWAHARA A, SATO Y. Prediction of the single-phase turbulent mixing rate between two parallel subchannels using a subchannel geometry factor[J]. Nuclear Engineering and Design, 1996, 162(2-3): 245-256. doi: 10.1016/0029-5493(95)01129-3
    [6]
    BUES S G. Two phase turbulent mixing model for flow in rod bundle: WAPD-T-2438[R]. Pittsburgh: Bettis Atomic Power Laboratory, 1972.
    [7]
    AVRAMOVA M. Development of an innovative spacer grid model utilizing computational fluid dynamics within a subchannel analysis tool[D]. University Park: The Pennsylvania State University, 2007.
    [8]
    LEVY S. Prediction of two-phase pressure drop and density distribution from mixing length theory[J]. Journal of Heat Transfer, 1963, 85(2): 137-150. doi: 10.1115/1.3686033
    [9]
    SADATOMI S, KAWAHARA A, SATO Y. Flow redistribution due to void drift in two-phase flow in a multiple channel consisting of two subchannels[J]. Nuclear Engineering and Design, 1994, 148(2-3): 463-474. doi: 10.1016/0029-5493(94)90126-0
    [10]
    HOTTA A, SHIRAI H, AZUMA M, et al. A modified equilibrium void distribution model applicable to subchannel-scale vapor-liquid cross flow model for conventional square and tight lattice BWR fuel bundles[J]. Nuclear Engineering and Design, 2005, 235(9): 983-999. doi: 10.1016/j.nucengdes.2004.10.012
    [11]
    SADATOMI M, KAWAHARA A, KANO K, et al. Single- and two-phase turbulent mixing rate between adjacent subchannels in a vertical 2 × 3 rod array channel[J]. International Journal of Multiphase Flow, 2004, 30(5): 481-498. doi: 10.1016/j.ijmultiphaseflow.2004.03.001
    [12]
    LAHEY R T JR, SHIRALKAR B S, RADCLIFFE D W, et al. Out-of-pile subchannel measurements in a nine-rod bundle for water at 1000 PSIA[J]//HETSRONI G, SIDEMAN S, HARTNETTJ P. Proceedings of the international symposium on two-phase systems: Progress in Heat and Mass Transfer. Amsterdam: Elsevier, 1972: 345-363.
    [13]
    VAN DER ROSS T. On two-phase exchange between interacting hydraulic channels[D]. Eindhoven: Eindhoven University of Technology, 1970.
    [14]
    TAPUCU A, TEYSSEDOU A, TYE P, et al. The effect of turbulent mixing models on the predictions of subchannel codes[J]. Nuclear Engineering and Design, 1994, 149(1-3): 221-231. doi: 10.1016/0029-5493(94)90288-7
  • 加载中

Catalog

    通讯作者: 陈斌, bchen63@163.com
    • 1. 

      沈阳化工大学材料科学与工程学院 沈阳 110142

    1. 本站搜索
    2. 百度学术搜索
    3. 万方数据库搜索
    4. CNKI搜索

    Figures(4)  / Tables(3)

    Article Metrics

    Article views (368) PDF downloads(56) Cited by()
    Proportional views
    Related

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return