Advance Search
Volume 43 Issue S1
Jul.  2022
Turn off MathJax
Article Contents
Tang Peng, Yao Di, Yu Li, Luo Juan, Zhou Ding. Mechanical Analysis of Pressure Vessels and Main Pipes under Steam Explosion Loads[J]. Nuclear Power Engineering, 2022, 43(S1): 127-131. doi: 10.13832/j.jnpe.2022.S1.0127
Citation: Tang Peng, Yao Di, Yu Li, Luo Juan, Zhou Ding. Mechanical Analysis of Pressure Vessels and Main Pipes under Steam Explosion Loads[J]. Nuclear Power Engineering, 2022, 43(S1): 127-131. doi: 10.13832/j.jnpe.2022.S1.0127

Mechanical Analysis of Pressure Vessels and Main Pipes under Steam Explosion Loads

doi: 10.13832/j.jnpe.2022.S1.0127
  • Received Date: 2021-11-05
  • Rev Recd Date: 2022-03-04
  • Publish Date: 2022-06-15
  • The mechanical response of HPR1000 reactor pressure vessel (RPV) and its main pipe under the hypothetical steam explosion load is studied. Through the establishment of the finite element model and the numerical analysis according to the transient structure analysis method, the deformation, stress and strain results of RPV and the main pipeline are obtained. The results show that the failure loads of RPV at 600℃, 800℃ and 1000℃ are 1/20, 1/50 and 1/100 design loads respectively; The maximum equivalent stress/strain is located near the nozzle; The stress in most areas of the main pipe does not exceed the yield stress of the pipe. This study can provide technical support for structural integrity analysis of RPV under extreme load.

     

  • loading
  • [1]
    U. S. Nuclear Regulatory Commission, Steam Explosion Review Group. A review of current understanding of the potential for containment failure arising from in-vessel steam explosion: NUREG-1116[R]. Washington: U. S. Nuclear Regulatory Commission, 1985.
    [2]
    THEOFANOUS T G. The study of steam explosions in nuclear systems[J]. Nuclear Engineering and Design, 1995, 155(1-2): 1-26. doi: 10.1016/0029-5493(94)00864-U
    [3]
    LESKOVAR M, URŠIČ M. Estimation of ex-vessel steam explosion pressure loads[J]. Nuclear Engineering and Design, 2009, 239(11): 2444-2458. doi: 10.1016/j.nucengdes.2009.07.023
    [4]
    LESKOVAR M, CENTRIH V, URŠIČ M. Simulation of steam explosion in stratified melt-coolant configuration[J]. Nuclear Engineering and Design, 2016, 296: 19-29. doi: 10.1016/j.nucengdes.2015.10.026
    [5]
    AHN K I, PARK S H, KIM H D, et al. The plant-specific uncertainty analysis for an ex-vessel steam explosion-induced pressure load using a TEXAS–SAUNA coupled system[J]. Nuclear Engineering and Design, 2012, 249: 400-412. doi: 10.1016/j.nucengdes.2012.04.015
    [6]
    MORIYAMA K, PARK H S. Probability distribution of ex-vessel steam explosion loads considering influences of water level and trigger timing[J]. Nuclear Engineering and Design, 2015, 293: 292-303. doi: 10.1016/j.nucengdes.2015.07.062
    [7]
    GRISHCHENKO D, GALUSHIN S, KUDINOV P. Failure domain analysis and uncertainty quantification using surrogate models for steam explosion in a Nordic type BWR[J]. Nuclear Engineering and Design, 2019, 343: 63-75. doi: 10.1016/j.nucengdes.2018.12.013
    [8]
    黄熙,杨燕华,王溪. 堆外蒸汽爆炸堆腔压力冲量分布计算分析[J]. 核动力工程,2011, 32(3): 15-21.
    [9]
    钟明君,林萌,张政铭,等. 基于1000 MW级压水堆核电厂压力容器外蒸汽爆炸的模拟研究[J]. 核动力工程,2014, 35(4): 43-47.
    [10]
    张荣金, 白伟, 倪伟峰, 等. 核电站堆外蒸汽爆炸影响因素探讨[C]//第十八届中国科协年会——分6军民融合高端论坛论文集. 西安: 中国科学技术协会学会学术部, 2016: 189-196.
    [11]
    李春,杨志义,丁超,等. 基于MC3D软件对核电厂压力容器蒸汽爆炸的重要参数计算及研究[J]. 核安全,2018, 17(2): 58-65.
  • 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)  / Tables(1)

    Article Metrics

    Article views (55) PDF downloads(8) Cited by()
    Proportional views
    Related

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return