• Journal of the Korean Society for Nondestructive Testing
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• v.33 no.6
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• pp.505-510
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• 2013

An encircling send-receive type pulsed eddy current (PEC) probe is designed for use in aluminum tube inspection. When bare receive coils located away from the exciter were used, the peak time of the signal did not change although the distance from the exciter increased. This is because the magnetic flux from the exciter coil directly affects the receive coil signal. Therefore, in this work, both the exciter and the sensor coils were shielded in order to reduce the influence of direct flux from the exciter coil. Numerical simulation with the designed shielded encircling PEC probe showed the corresponding increase of the peak time as the sensor distance increased. Ferrite and carbon steel shields were compared and results of the ferrite shielding showed a slightly stronger peak value and a quicker peak time than those of the carbon steel shielding. Simulation results showed that the peak value increased as the defect size (such as depth and length) increased regardless of the sensor location. To decide a proper sensor location, the sensitivity of the peak value to defect size variation was investigated and found that the normalized peak value was more sensitive to defect size variation when the sensor was located closer to the exciter.

• Journal of the Korean Society for Nondestructive Testing
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• v.21 no.5
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• pp.561-564
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• 2001

The cladding area of HANARO Research Reactor fuel rods should be checked not to have any defects larger than the size required at QA documents by using eddy torrent testing method doting fabrication process. To apply eddy current testing inspection to the fuel rods, encircling differential probes and standard specimen were designed and fabricated. The impedance of the fabricated probes was measured with impedance analyzer in order to cheek that the probe has a suitable impedance for the inspection frequency, and with this probe and MIZ-40A eddy current equipment, the detectability of this probes was investigated. The developed probes could detect artificial notch with 2mm length 10% depth of cladding thickness in cladding area. In addition, the probe was successfully applied to detect the defects in cladding area doting fabrication of the research reactor rods.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.10a
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• pp.302-302
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• 1998

• Proceedings of the Korean Nuclear Society Conference
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• 2002.05a
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• pp.249.1-249
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• 2002

• Proceedings of the Korean Nuclear Society Conference
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• 1999.10a
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• pp.206.2-206
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• 1999

• Journal of the Korean Society for Nondestructive Testing
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• v.21 no.6
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• pp.650-657
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• 2001

This paper explains the process of designing a shielded encircling remote field eddy current (RFEC) probe to inspect nuclear fuel cladding tubes and investigates resulting signal characteristics. To force electromagnetic energy from exciter coil to penetrate into the tube, exciter coil is shielded outside by laminations of iron insulated electrically from each other. Effects of shielding and the proper operating frequency are studied by the finite element analysis and the location for sensor coil is decided. However, numerically simulated signals using the designed probe do not clearly show the defect indication when the sensor passes a defect and the other indication appeared as the exciter passes the defect is affected by the shape of shielding structure, which demonstrates that the sensor is directly affected by exciter fields. For this reason, the sensor is also shielded outside and this shielding dramatically improves signal characteristics. Numerical modeling with the finally designed probe shows very similar signal characteristics to those of inner diameter RFEC probe. That is, phase signals show almost equal sensitivity to inner diameter and outer diameter defects and the linear relationship between phase signal strength and defect depth is observed.

• Proceedings of the Korean Nuclear Society Conference
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• 2005.10a
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• pp.159-160
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• 2005

• Proceedings of the KIEE Conference
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• 1999.07a
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• pp.290-292
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• 1999

핵연료봉이나 제어봉과 같은 봉구조물의 검사를 위하여 원격장와전류 효과를 낼 수 있는 탐촉자를 설계하고 탐상주파수를 유한요소해석을 통해 설정하였다. 핵연료봉을 대상으로 한 해석에서 exciter coil 주변을 차폐하고 500kHz의 주파수를 사용한 결과 전위계곡과 위상매듭의 존재가 나타나 원격장와전류 효과가 구현되었음을 확인하였다. exciter와 sensor coil로 이루어진 탐촉자를 이동시키면서 예측한 탐상신호에서는 센서를 원격장 의치에 고정시켰을 때, 결함이 센서를 지날 때의 위상신호와 결함이 exciter를 지날 때의 위상신호가 서로 달리 나타났다. 또한, 외부결함과 내부결함이 센서를 지날 때의 위상지연은 작지만 서로 반대의 경향으로 나타났으며, 두 종류의 결함이 exciter를 지날 때는 위상지연이 상대적으로 크게 줄어들고 외부/내부 결함에 상관없이 신호가 비슷하게 나타남을 볼 수 있었다. 이러한 신호형태는 자성체 관의 탐상에서 내, 외부 결함신호가 구별이 안되고, 동일한 위상신호가 항상 쌍으로 나타나는 것과 비교할 때, 신호해석을 훨씬 수월하게 해 줄 수 있을 것이라고 판단된다.

• Journal of the Korean Society for Nondestructive Testing
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• v.35 no.5
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• pp.291-298
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• 2015

An array type probe for monitoring metal tubes is proposed in this paper which utilizes peak value and peak time of a pulsed eddy current(PEC) signal. The probe consists of an array of encircling coils along a tube and the outside of coils is shielded by ferrite to prevent source magnetic fields from directly affecting sensor signals since it is the magnetic fields produced by eddy currents that reflect the condition of metal tubes. The positions of both exciter and sensor coils are consecutively moved automatically so that manual scanning is not necessary. At one position of send-receive coils, peak value and peak time are extracted from a sensor PEC signal and these data are accumulated for all positions to form an array type peak value signal and an array type peak time signal. Numerical simulation was performed using the backward difference method in time and the finite element method for spatial analysis. Simulation results showed that peak value increases and the peak appears earlier as the defect depth or length increases. The proposed array signals are shown to be excellent in reflecting the defect location as well as variations of defect depth and length within the array probe.

• Journal of the Korean Society for Nondestructive Testing
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• v.16 no.1
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• pp.29-33
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• 1996

The eddy current test(ECT) probe of differential encircling coil type was designed and fabricated, and the optimum condition of ECT was derived for the examination of the irradiated fuel rod. The correlation between ECT test frequency and phase & amplitude was derived by performing the test of the standard rig that includes inner notches, outer notches and through-holes. The defect of through-hole was predicted by ECT at the G33-N2 fuel rod irradiated in the Kori-1 nuclear power reactor. The metallographic examination on the G33-N2 fuel rod was Performed at the defect location predicted by ECT. The result of metallographic examination for the G33-N2 fuel rod was in good agreement with that of ECT. This proves that the evaluation for integrity of irradiated fuel rod by ECT is reliable.