核反应堆控制棒涡流检测仿真

基金项目:

大型先进压水堆及高温气冷堆核电站国家科技重大专项资助项目（2016ZX06004003）

详细信息

Simulation on Eddy Current Testing for Control Rod of Nuclear Reactor

摘要: 采用CIVA软件对核反应堆控制棒磨损、裂纹缺陷的涡流检测信号进行仿真与分析。结果表明：涡流信号的幅值和相位分别与缺陷截面损失、缺陷深度线性相关，可对缺陷进行定量表征。构造了缺陷-幅值-相位图，其可以作为缺陷类型判定的重要依据。该研究结果为控制棒涡流检测的缺陷评估提供了参考。
- 控制棒 /
- 涡流检测 /
- 缺陷评估
Abstract: This paper presents simulation studies on eddy current signals resulted from wear and crack in control rod of nuclear reactor using CIVA. The results show that:the amplitude and phase of eddy current signal can be linearly related to the cross section loss and defect depth, thus they can be used in the quantitative characterization of defect. The proposed defect-amplitude-phase map may become an important indicator for defect type determination. The study provides reference for defect evaluation in the eddy current testing of control rod.
- control rod /
- eddy current testing /
- defect evaluation

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