Advance Search
Volume 43 Issue 6
Dec.  2022
Turn off MathJax
Article Contents
Liu Wenbin, Deng Caiyu, Song Jiyang, Xiang Yuxin, Kang Changhu, Liu Chang, Song Yuge, Guo Yufei. Study on Flow Blockage Accident of HFETR Multi-layer Annular Fuel Assembly[J]. Nuclear Power Engineering, 2022, 43(6): 117-121. doi: 10.13832/j.jnpe.2022.06.0117
Citation: Liu Wenbin, Deng Caiyu, Song Jiyang, Xiang Yuxin, Kang Changhu, Liu Chang, Song Yuge, Guo Yufei. Study on Flow Blockage Accident of HFETR Multi-layer Annular Fuel Assembly[J]. Nuclear Power Engineering, 2022, 43(6): 117-121. doi: 10.13832/j.jnpe.2022.06.0117

Study on Flow Blockage Accident of HFETR Multi-layer Annular Fuel Assembly

doi: 10.13832/j.jnpe.2022.06.0117
  • Received Date: 2021-11-16
  • Rev Recd Date: 2022-03-29
  • Publish Date: 2022-12-14
  • The fuel assembly of High Flux Engineering Test Reactor (HFETR) adopts multi-layer annular narrow slot flow channel design to improve the heat transfer capacity. However, it should be noted that the narrow slot flow channel is more likely to be blocked. In this paper, the HFETR fuel assembly model is established based on the RELAP5 program. The comparison between the calculated value and the experimental value shows that the model is reasonable and accurate. Based on the model, the transient characteristics and influencing factors of hot box fuel assembly under flow blockage accident are studied. The results show that: ① When the flow blockage ratio is greater than 0.5, the peak temperature of fuel cladding and core increases significantly with the increase of flow blockage ratio; ② Even if a single flow channel is blocked completely, due to the cooling of the surrounding flow channels, the maximum peak temperature of the fuel cladding is only 218.6 ℃, which can ensure the integrity of the fuel cladding; ③ The flow rate and other parameters fluctuate greatly at the initial stage of a single flow channel full blockage accident, but the main parameters of the fuel assembly are basically stable 15 s after the accident.

     

  • loading
  • [1]
    刘天才,金华晋,袁履正. 中国先进研究堆堵流事故分析[J]. 核动力工程,2006, 27(S2): 32-35,44.
    [2]
    丁丽,骆贝贝,花晓,等. 板状燃料元件流道堵塞事故预防与探测技术研究[J]. 核技术,2020, 43(4): 7-13.
    [3]
    SALAMA A, EL-MORSHEDY S E D. CFD analysis of flow blockage in MTR coolant channel under loss-of-flow transient: hot channel scenario[J]. Progress in Nuclear Energy, 2012, 55: 78-92. doi: 10.1016/j.pnucene.2011.11.005
    [4]
    ADORNI M, BOUSBIA-SALAH A, HAMIDOUCHE T, et al. Analysis of partial and total flow blockage of a single fuel assembly of an MTR research reactor core[J]. Annals of Nuclear Energy, 2005, 32(15): 1679-1692. doi: 10.1016/j.anucene.2005.06.001
    [5]
    GUO Y C, WANG G B, QIAN D Z, et al. Thermal hydraulic analysis of loss of flow accident in the JRR-3M research reactor under the flow blockage transient[J]. Annals of Nuclear Energy, 2018, 118: 147-153. doi: 10.1016/j.anucene.2018.04.014
    [6]
    SON H M, YANG S H, PARK C. Transient thermal–hydraulic analysis of complete single channel blockage accident of generic 10 MW research reactor[J]. Annals of Nuclear Energy, 2015, 75: 44-53. doi: 10.1016/j.anucene.2014.08.002
    [7]
    YUAN D D, DENG J, HAN R, et al. Experimental study on flow structures of central blockage accidents in a rectangular channel using PIV and POD[J]. Annals of Nuclear Energy, 2021, 153: 108037. doi: 10.1016/j.anucene.2020.108037
  • 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(5)  / Tables(1)

    Article Metrics

    Article views (186) PDF downloads(29) Cited by()
    Proportional views
    Related

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return