Advance Search
Volume 44 Issue 3
Jun.  2023
Turn off MathJax
Article Contents
Cai Qinghang, Chen Ronghua, Xiao Xinkun, Fu Hao, Tian Wenxi, Qiu Suizheng, Su Guanghui. Experiment Research on the Mechanism of Fuel Migration Behavior under Severe Accident of Lead-based Reactor[J]. Nuclear Power Engineering, 2023, 44(3): 90-95. doi: 10.13832/j.jnpe.2023.03.0090
Citation: Cai Qinghang, Chen Ronghua, Xiao Xinkun, Fu Hao, Tian Wenxi, Qiu Suizheng, Su Guanghui. Experiment Research on the Mechanism of Fuel Migration Behavior under Severe Accident of Lead-based Reactor[J]. Nuclear Power Engineering, 2023, 44(3): 90-95. doi: 10.13832/j.jnpe.2023.03.0090

Experiment Research on the Mechanism of Fuel Migration Behavior under Severe Accident of Lead-based Reactor

doi: 10.13832/j.jnpe.2023.03.0090
  • Received Date: 2022-07-13
  • Rev Recd Date: 2022-08-30
  • Publish Date: 2023-06-15
  • In the severe accident of lead-based reactor, the fuel particles may lead to core blockage during the migration process in the reactor, and there is a risk of re-criticality. In this study, in order to obtain the flow and migration characteristics of metal particles entrained in liquid lead-bismuth eutectic (LBE), the visualization experimental section of quartz glass was designed, and the visual experimental device called Eirene for the flow and solidification behavior of LBE entrained particles was built. And the flow solidification experiment of LBE in a circular channel and that of LBE entrained stainless steel particles were carried out. The image data of flow and solidification characteristic of LBE, the temperature data of inlet, outlet and tube wall were obtained. The results show that the existence of metal particles seriously hinder the flow of LBE in the tube. It is easy to form solidification blockage in the dense area of the particle bed. A large number of particles are anchored in the middle of the experimental section and gradually form blockage from the outside to the inside. The experimental results can provide support for the verification of the lead-based reactor severe accident analysis models.

     

  • loading
  • [1]
    GIF Policy Group. Technology roadmap update for Generation IV nuclear energy systems[Z]. USA: OECD Nuclear Energy Agency for the Generation IV International Forum, 2014.
    [2]
    魏诗颖,王成龙,田文喜,等. 铅基快堆关键热工水力问题研究综述[J]. 原子能科学技术,2019, 53(2): 326-336.
    [3]
    WANG J, TIAN W X, TIAN Y H, et al. A sub-channel analysis code for advanced lead bismuth fast reactor[J]. Progress in Nuclear Energy, 2013, 63: 34-48. doi: 10.1016/j.pnucene.2012.09.010
    [4]
    SHI L T, TAN B, WANG C L, et al. Experimental investigation of gas lift pump in a lead-bismuth eutectic loop[J]. Nuclear Engineering and Design, 2018, 330: 516-523. doi: 10.1016/j.nucengdes.2018.01.042
    [5]
    苏光辉, 秋穗正, 田文喜. 核动力系统热工水力计算方法[M]. 北京: 清华大学出版社, 2013: 263
    [6]
    汪振. 铅基研究实验堆假想堆芯解体事故分析研究[D]. 合肥: 中国科学技术大学, 2017.
    [7]
    苏光辉, 田文喜, 张亚培, 等. 轻水堆核电厂严重事故现象学[M]. 北京: 国防工业出版社, 2016: 77-80.
    [8]
    WANG J S, CAI Q H, CHEN R H, et al. Numerical analysis of melt migration and solidification behavior in LBR severe accident with MPS method[J]. Nuclear Engineering and Technology, 2022, 54(1): 162-176. doi: 10.1016/j.net.2021.07.043
    [9]
    RAHMAN M M, HINO T, MORITA K, et al. Experimental investigation of molten metal freezing on to a structure[J]. Experimental Thermal and Fluid Science, 2007, 32(1): 198-213. doi: 10.1016/j.expthermflusci.2006.11.009
    [10]
    HOSSAIN M K, HIMURO Y, MORITA K, et al. Experimental study of molten metal penetration and freezing behavior in pin-bundle geometry[J]. Memoirs of the Faculty of Engineering, Kyushu University, 2008, 68(4): 163-174.
    [11]
    YAMANO H, TOBITA Y. Experimental analyses by SIMMER-III on molten fuel freezing and boiling pool behavior[J]. Journal of Power and Energy Systems, 2009, 3(1): 249-260. doi: 10.1299/jpes.3.249
    [12]
    Soner M A M, HASEGAWA Y, SEO S, et al. Experimental investigation of solid–liquid mixtures freezing behavior in flow channels[J]. Nuclear Engineering and Design, 2011, 241(10): 4223-4235. doi: 10.1016/j.nucengdes.2011.08.027
    [13]
    CHEN R H, CHEN L, GUO K L, et al. Numerical analysis of the melt behavior in a fuel support piece of the BWR by MPS[J]. Annals of Nuclear Energy, 2017, 102: 422-439. doi: 10.1016/j.anucene.2017.01.007
    [14]
    CHEN R H, LI Y L, GUO K K, et al. Numerical investigation on the dissolution kinetics of ZrO2 by molten zircaloy using MPS method[J]. Nuclear Engineering and Design, 2017, 319: 117-125. doi: 10.1016/j.nucengdes.2017.05.002
    [15]
    CAI Q H, ZHU D H, CHEN R H, et al. Three-dimensional numerical study on the effect of sidewall crust thermal resistance on transient MCCI by improved MPS method[J]. Annals of Nuclear Energy, 2020, 144: 107525. doi: 10.1016/j.anucene.2020.107525
    [16]
    XIAO X K, CAI Q H, CHEN R H, et al. An improved MPS-DEM numerical model for fluid–solid coupling problem in nuclear reactor[J]. Nuclear Engineering and Design, 2022, 396: 111875. doi: 10.1016/j.nucengdes.2022.111875
    [17]
    DING W, XIAO X K, CAI Q H, et al. Numerical investigation of fluid–solid interaction during debris bed formation based on MPS-DEM[J]. Annals of Nuclear Energy, 2022, 175: 109244. doi: 10.1016/j.anucene.2022.109244
  • 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(9)

    Article Metrics

    Article views (1967) PDF downloads(58) Cited by()
    Proportional views
    Related

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return