Advance Search
Volume 43 Issue 5
Oct.  2022
Turn off MathJax
Article Contents
Zhang Ruikai, Liu Pan, Tan Jianping, Li Yue, Wang Dasheng, Tu Shandong. Calculation of Stress Intensity Factor of External Surface Crack on the Nozzle of Steam Generator in Nuclear Power Plant[J]. Nuclear Power Engineering, 2022, 43(5): 138-146. doi: 10.13832/j.jnpe.2022.05.0138
Citation: Zhang Ruikai, Liu Pan, Tan Jianping, Li Yue, Wang Dasheng, Tu Shandong. Calculation of Stress Intensity Factor of External Surface Crack on the Nozzle of Steam Generator in Nuclear Power Plant[J]. Nuclear Power Engineering, 2022, 43(5): 138-146. doi: 10.13832/j.jnpe.2022.05.0138

Calculation of Stress Intensity Factor of External Surface Crack on the Nozzle of Steam Generator in Nuclear Power Plant

doi: 10.13832/j.jnpe.2022.05.0138
  • Received Date: 2021-09-26
  • Accepted Date: 2021-11-12
  • Rev Recd Date: 2021-11-06
  • Publish Date: 2022-10-12
  • Due to the particularity of its structure, the nozzle of the nuclear steam generator (SG) is prone to defects during manufacturing and operating process. In order to evaluate the safety of the defect, the stress intensity factor solution available in engineering is required. In this paper, taking the external surface crack of nuclear SG nozzle as the research object, the equivalent stress intensity factors of cracks in different directions and sizes under internal pressure, bending moment and temperature loads are calculated by finite element method and RSE-M code, and the distribution law of equivalent stress intensity factors at the crack front under different loads is analyzed. By comparing the calculation results with the straight pipe stress intensity factor solution of RSE-M code, it is found that the straight pipe stress intensity factor calculation method of RSE-M code can be conservatively applied to the cracks at SG nozzle, and the conservation increases with increasing crack depth. In order to realize the accurate evaluation of the defect safety of SG nozzle, a calculation method of stress intensity factor applicable to the cracks on the external surface of SG nozzle is given based on finite element calculation and RSE-M influence coefficient method, which can provide guidance for the design and maintenance of SG nozzle.

     

  • loading
  • [1]
    AFCEN. RSE-M: in-service inspection rules for mechanical components of PWR nuclear islands[M]. Paris: French Association for Design, Construction and In-Service Inspection Rules for Nuclear Island Components, 2010.
    [2]
    ASME. Rules for construction of pressure vessels, Division 3, Alternative rules for construction of high pressure vessels: ASME BPVC VIII-3[S]. New York: The American Society of Mechanical Engineering, 2010.
    [3]
    NEWMAN JR J C, RAJU I S. Stress-intensity factors for internal surface cracks in cylindrical pressure vessels[J]. Journal of Pressure Vessel Technology, 1980, 102(4): 342-346. doi: 10.1115/1.3263343
    [4]
    NEWMAN J C, RAJU I S. Stress-intensity factor equations for cracks in three-dimensional finite bodies[M]. Philadelphia: ASTM Special Technical Publication, 1983: 238-265.
    [5]
    ISMAIL A E, ARIFFIN A K, ABDULLAH S, et al. Stress intensity factors for surface cracks in round bar under single and combined loadings[J]. Meccanica, 2012, 47(5): 1141-1156. doi: 10.1007/s11012-011-9500-7
    [6]
    DIAMANTOUDIS A T, LABEAS G N. Stress intensity factors of semi-elliptical surface cracks in pressure vessels by global-local finite element methodology[J]. Engineering Fracture Mechanics, 2005, 72(9): 1299-1312. doi: 10.1016/j.engfracmech.2004.10.004
    [7]
    CHAPULIOT S. Stress intensity factor calculation in sharp and beveled edge nozzle corners[J]. International Journal of Pressure Vessels and Piping, 2016, 141: 11-18. doi: 10.1016/j.ijpvp.2016.03.015
    [8]
    LI Y B, JIN T, WANG Z H, et al. Engineering critical assessment of RPV with nozzle corner cracks under pressurized thermal shocks[J]. Nuclear Engineering and Technology, 2020, 52(11): 2638-2651. doi: 10.1016/j.net.2020.04.019
    [9]
    王大胜,刘攀,熊光明. 考虑接管载荷的反应堆压力容器接管嘴断裂力学分析[J]. 核动力工程,2015, 36(5): 120-123.
    [10]
    张丽屏,苏东川,高世卿,等. 反应堆压力容器接管嘴内隅角应力强度因子计算研究[J]. 原子能科学技术,2017, 51(11): 2042-2048. doi: 10.7538/yzk.2017.youxian.0275
    [11]
    李东方,杨海波,毛朝晖,等. 热交换管内壁子午面半椭圆裂纹应力强度因子数值计算[J]. 机电工程,2020, 37(3): 253-258.
    [12]
    张兴田. 基于RSE-M规范核电厂反应堆压力容器堆焊层缺陷的断裂力学分析与评定[J]. 机械工程材料,2016, 40(12): 32-36,82. doi: 10.11973/jxgccl201612008
  • 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(12)  / Tables(1)

    Article Metrics

    Article views (180) PDF downloads(49) Cited by()
    Proportional views
    Related

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return