Advance Search
Volume 44 Issue S1
Jun.  2023
Turn off MathJax
Article Contents
Ding Lei, Chen Xing, Wang Dianle, Xu Jianjun, Sui Xi, Fang Ying, Meng Yang. Experiment Research on Integral Hydraulic Simulation of ACP100 Reactor[J]. Nuclear Power Engineering, 2023, 44(S1): 29-34. doi: 10.13832/j.jnpe.2023.S1.0029
Citation: Ding Lei, Chen Xing, Wang Dianle, Xu Jianjun, Sui Xi, Fang Ying, Meng Yang. Experiment Research on Integral Hydraulic Simulation of ACP100 Reactor[J]. Nuclear Power Engineering, 2023, 44(S1): 29-34. doi: 10.13832/j.jnpe.2023.S1.0029

Experiment Research on Integral Hydraulic Simulation of ACP100 Reactor

doi: 10.13832/j.jnpe.2023.S1.0029
  • Received Date: 2023-02-21
  • Rev Recd Date: 2023-05-17
  • Publish Date: 2023-06-15
  • Advanced Small Modular Pressurized Reactor (ACP100) is a new integrated small-scale reactor. Its once-through steam generators and reactor coolant pumps are directly integrated into the pressure vessel, and the compact design leads to a complex internal flow field. A 1/3 scaled-down model was used to simulate the entire internal flow field of the ACP100 reactor and carry out integral hydraulic simulation cold experiment for the reactor. In the experiment, the total pressure drop and segmented pressure drop of the model were obtained, as well as the total resistance coefficient and the segmented resistance coefficients of the main flow paths. The flow distribution factors of each fuel assembly at the core inlet were also acquired. The experiment results showed that the flow inside the main channels had entered the second self-modeling zone, and the flow pattern, velocity distribution and resistance coefficient of the fluid were consistent with those of the prototype reactor. After entering the second self-modeling zone, the total resistance coefficient of the model remained constant at 8.02, which can be used to calculate the pressure drop of the prototype directly. Under rated operating condition, all the distribution factors at the core inlet ranged from 0.91 to 1.08, meeting the design requirements. Besides, the flow distribution of LOFA simulation was uniform, indicating that the flow distributor had good rectifying effects.

     

  • loading
  • [1]
    王建民,李经纬. 秦山核电二期工程反应堆水力学设计[J]. 核动力工程,2003, 24(S2): 24-27.
    [2]
    眭曦,王盛,杨祖毛,等. 中国工程试验堆堆芯入口流量分配特性实验研究[J]. 原子能科学技术,2020, 54(2): 257-263. doi: 10.7538/yzk.2019.youxian.0105
    [3]
    HETSRONI G. Use of hydraulic models in nuclear reactor design: NYO-3250-2[R]. Haddam: Connecticut Yankee Atomic Power Co., 1965.
    [4]
    HENSCH F. JULIETTE tests interpretation flow rate distribution and characterization of the head losses and pressure fields: NFPSDDC 1025[R]. Areva: Areva Group, 2006.
    [5]
    EUH D J, KWON T S, YOUN Y J, et al. Hydraulic characteristics of SMART reactor for a nominal condition[C]//Proceedings of the 9th International Conference on Heat Transfer, Fluid Mechanics and Thermodynamics. Malta: International Conference on Heat Transfer, Fluid Mechanics and Thermodynamics, 2012.
    [6]
    杨来生,宗桂芳,胡俊. 秦山核电二期工程反应堆水力模拟实验研究[J]. 核动力工程,2003, 24(S1): 208-211,226.
    [7]
    KHAN E U. Analytical investigation and design of a model hydro-dynamically simulating a prototype PWR core[J]. Nuclear Technology, 1972, 16(3): 479-496. doi: 10.13182/NT72-A31217
  • 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(8)  / Tables(1)

    Article Metrics

    Article views (262) PDF downloads(58) Cited by()
    Proportional views
    Related

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return