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基于柔性涡流探头的托卡马克内部线圈导体偏心涡流检测

赵宏达, 李勇, 刘小川, 武玉

赵宏达, 李勇, 刘小川, 武玉. 基于柔性涡流探头的托卡马克内部线圈导体偏心涡流检测[J]. 无损检测, 2014, 36(11): 11-13.
引用本文: 赵宏达, 李勇, 刘小川, 武玉. 基于柔性涡流探头的托卡马克内部线圈导体偏心涡流检测[J]. 无损检测, 2014, 36(11): 11-13.
Eddy Current Testing of Eccentricity in Tokamak In-Vessel Coil Conductors Based on Flexible Probe[J]. Nondestructive Testing, 2014, 36(11): 11-13.
Citation: Eddy Current Testing of Eccentricity in Tokamak In-Vessel Coil Conductors Based on Flexible Probe[J]. Nondestructive Testing, 2014, 36(11): 11-13.

基于柔性涡流探头的托卡马克内部线圈导体偏心涡流检测

基金项目: 

国家自然科学基金资助项目(51277139,11321062)

国家磁约束聚变资助项目(2013GB113005)

国家973资助项目(2011CB610303)

详细信息
    作者简介:

    赵宏达(1989-),男,助理工程师,主要从事电磁无损检测和渗透检测研究。

  • 中图分类号: TG115.28

Eddy Current Testing of Eccentricity in Tokamak In-Vessel Coil Conductors Based on Flexible Probe

  • 摘要: 托卡马克内部线圈由具有三层结构的套管导体绕制而成。在其加工过程中,可能会产生偏心缺陷,导致中间氧化镁陶瓷层绝缘性能下降,进而可能造成严重后果。因此,对其偏心缺陷进行有效的无损检测尤为重要。为提高涡流检测方法对于偏心缺陷的检测能力,降低提离变化等导致的误差,提出和验证了基于柔性涡流探头进行偏心检测的方法,并通过不同探头结构及放置方式下检出效果的对比,探讨了最优探头配置方式。
    Abstract: The conductor of ITER In-Vessel Coil (IVC) is of three-layer tubular structure. During manufacture procedure of IVCs, eccentricity may occur between the copper tube conductor and stainless-steel supporting tube. Large eccentricity may seriously reduce the insulation property of the middle ceramic layer of IVC conductor and cause big influence on the performance of entire IVC. Therefore, it is critical to evaluate the eccentricity of IVCs by using non-destructive testing techniques. Our group has proposed an eddy current testing method based on absolute pancake coil in earlier studies. To enhance the evaluation efficiency of the eddy current testing method and to improve evaluation precision, in this paper, ECT based on TR type flexible probe is proposed and its detect ability is demonstrated. In addition, optimized probe structure and arrangement are also investigated by comparing the detect ability of different probe structures.
  • [1] SCHAFFER M J, MENARD J E, ALDAN M P, et al. Study of in-vessel nonaxisymmetric ELM suppression coil concepts for ITER[J]. Nuclear Fusion, 2008, 48(2): 1-14.
    [2] VILLARI R, PETRIZZI L, BROLATTI G, et al. Three-dimensional neutronic analysis of the ITER in-vessel coils[J]. Fusion Engineering and Design, 2011, 86(6): 584-587.
    [3] YONG L, CHEN Z, MAO Y, et al. Quantitative evaluation of thermal barrier coating based on eddy current technique[J]. NDT & E International, 2012, 50: 29-35.
    [4] 任吉林,林俊明. 电磁无损检测[M]. 北京:科学出版社,2008.
    [5] 赵宏达,蔡文路,李勇,等, 托卡马克内部线圈套管导体偏心缺陷无损检测方法研究[J] .无损检测,2013,32(10):63-66.
    [6] FUKTOMI H, TAKAGI T, NISHIKAWA M. Remote field eddy current technique applied to non-magnetic steam generator tubes[J]. NDT & E International, 2001, 34(1): 17-23.
    [7] NARDON E, BECOULET M, HUYSMANS G, et al. Edge localized modes control by resonant magnetic perturbations[J]. Journal of Nuclear Materials, 2007, 363: 1071-1075.
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出版历程
  • 收稿日期:  2014-06-24
  • 刊出日期:  2014-11-09

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