Advance Search
Volume 46 Issue 3
Jun.  2025
Turn off MathJax
Article Contents
Gan Wenjun, Cai Jiafan, Zhou Lifeng. Ultrasonic Inspection & Data Analysis for Failed Fuel Assembly[J]. Nuclear Power Engineering, 2025, 46(3): 249-252. doi: 10.13832/j.jnpe.2024.050046
Citation: Gan Wenjun, Cai Jiafan, Zhou Lifeng. Ultrasonic Inspection & Data Analysis for Failed Fuel Assembly[J]. Nuclear Power Engineering, 2025, 46(3): 249-252. doi: 10.13832/j.jnpe.2024.050046

Ultrasonic Inspection & Data Analysis for Failed Fuel Assembly

doi: 10.13832/j.jnpe.2024.050046
  • Received Date: 2024-05-21
  • Rev Recd Date: 2024-12-04
  • Available Online: 2025-06-09
  • Publish Date: 2025-06-09
  • To safely, effectively, and accurately locate failed fuel assemblies in nuclear power plants through ultrasonic inspection methods, this study utilizes the characteristic that the medium state of the inner wall of the fuel cladding before and after damage will cause differences in the attenuation of circumferential Lamb wave energy in the cladding. The propagation path of the Lamb wave in the fuel cladding during the movement of the ultrasonic probe in the gap between fuel assemblies is analyzed theoretically, and the propagation sound path is analyzed and calculated. The deviation between the calculated results and the measured values is within ±2%. Based on the principle of ultrasonic detection and the characteristics of sound beam propagation, the automatic identification algorithm and data analysis software of fuel rod cladding echo signal are developed, which can realize the rapid analysis and screening of detection data. The test results of simulated fuel assemblies and field application verify that the detection method is fast, safe and effective in detecting the damaged location of leaking rods in fuel assemblies, and the automatic signal identification algorithm and data analysis software are accurate and reliable, which can provide a basis for the targeted repair of damaged fuel assemblies in the future and improve the utilization rate of nuclear fuel.

     

  • loading
  • [1]
    吴中旺,张亚军. 定位检测破损燃料组件的堆芯啜吸法[J]. 清华大学学报: 自然科学版,2000, 40(12): 79-81.
    [2]
    贾亚青,李成业,李劲松,等. 微破损燃料组件离线检漏装置研制[J]. 核动力工程,2016, 37(1): 82-85.
    [3]
    许俊龙,马官兵,王贤彬,等. 核反应堆燃料组件的无损检测和修复[J]. 无损检测,2014, 36(11): 38-41.
    [4]
    任亮,李国云,江林志,等. 压水堆燃料组件池边检查技术研究进展[J]. 科技导报,2015, 33(18): 91-95.
    [5]
    BORGERS H, DELERYD R, OLSSON T. Inspection and repair of boiling water reactor fuel assemblies[J]. Kerntechnik, 1991, 56(2): 98-100. doi: 10.1515/kern-1991-560215
    [6]
    THOME Z D, PEREIRA W C A, MACHADO J C, et al. A system for nuclear fuel inspection based on ultrasonic pulse-echo technique[J]. IEEE Transactions on Nuclear Science, 2011, 58(5): 2452-2458. doi: 10.1109/TNS.2011.2164557
    [7]
    殷振国,王华才,刘歆粤,等. 燃料棒破损超声检测技术研究[J]. 原子能科学技术,2015, 49(2): 324-329.
    [8]
    WU B, SU Y P, CHEN W Q, et al. On guided circumferential waves in soft electroactive tubes under radially inhomogeneous biasing fields[J]. Journal of the Mechanics and Physics of Solids, 2017, 99: 116-145. doi: 10.1016/j.jmps.2016.11.004
    [9]
    李子明,何存富,刘增华,等. 管道周向导波检测技术研究进展及展望[J]. 北京工业大学学报,2018, 44(5): 641-657.
    [10]
    王坤,黄松岭,赵伟. 平板和管道周向Lamb波频散和波结构特性[J]. 清华大学学报: 自然科学版,2009, 49(7): 925-928.
    [11]
    牛雨欣,伍文君,董浩,等. 模态耦合对弯管导波传播特性的影响分析[J]. 武汉理工大学学报,2023, 45(4): 149-156.
  • 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(4)

    Article Metrics

    Article views (11) PDF downloads(2) Cited by()
    Proportional views
    Related

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return