• Journal of Welding and Joining
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• v.1 no.2
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• pp.7-11
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• 1983

본 공장(진해화학주식회사)에서 암모니아는 나프타를 원료로 한 수소와 공기 중의 질소를 합성하여 제조된다. 암모니아 제조 공정 중 메탄가스(CH$_{4}$)와 수소가스(H$_{2}$) 중에 불순물로 존재하는 유화 수소(H$_{2}$S)를 제거시키는 공정이 탈황공정이다. 탈황공정은 산화 아연(ZnO)과 코발트-몰리브덴(Cobalt-Molybdenum) 촉매층에서 이루어지며 탈황공정이 이루어지는 용기를 탈황조(desulfurizer vessel)라 한다. 본 공장에 설치된 탈황조는 1966년에 설치되어 운용되어 왔다. 본 공장의 안전 조업을 위해 초음파 탐상법, 방사선 투과 탐상법, 표면 침투 탐상법으로써 탈황조의 노후도 측정을 행하였다. 탐상 결과 스테인레스 클래드의 모재부 용접선을 따라 균열이 발견되었다. 균열 부위를 깊이 연마하여 용접 결함부를 제거하고 다시 용접을 함으로써 본 탈황조를 연장하여 사용할 수 있었다.

• Journal of the Korean Society for Nondestructive Testing
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• v.36 no.6
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• pp.483-489
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• 2016

The typical methods used for inspecting ferromagnetic pipes include the ultrasonic testing (UT) contact method and the following non-contact methods: magnetic flux leakage (MFL), electromagnetic acoustic transducers (EMAT), and remote field eddy current testing (RFECT). Among these methods, the RFECT method has the advantage of being able to establish a system smaller than the diameter of a pipe. However, the method has several disadvantages as well, including different sensitivities and difficult-to-repair coil sensors which comprise its array system. Therefore, a giant magneto-resistance (GMR) sensor was applied to address these issues. The GMR sensor is small, easy to replace, and has uniform sensitivity. In this experiment, the GMR sensor was used to measure remote field and defect signal characteristics (in the axial and radial directions) in a ferromagnetic pipe. These characteristics were measured in an effort to investigate standard defects at changing depths within a pipe. The results show that the experiment successfully demonstrated the applicability of the GMR sensor to RFECT signal detection in ferromagnetic pipe.

• Proceedings of the Korean Society of Precision Engineering Conference
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• 2010.11a
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• pp.721-722
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• 2010

• Journal of the Korean Society for Nondestructive Testing
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• v.28 no.1
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• pp.64-69
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• 2008

In order to detect the internal defects which occur in welding parts of pressure vessel and structures, radiographic testing and ultrasonic testing is applied. However, because of the risks of radiation exposure and film processing, radiographic testing takes a relatively long time to verify the test results and it has affected in the production process. Typically, the manual ultrasonic testing is not easy to reproduce the result and it is highly dependent on the tester's skills. The TOFD technique, one of the automatic ultrasonic testings is spreading alternatively. This research describes the comparing test results by applying radiographic testing and TOFD technique to a mock-up specimen incruding the flaws. The TOFD technique will contribute to improve the objective reliability of the ultrasonic technique.

• Proceedings of the Korea Concrete Institute Conference
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• 2008.04a
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• pp.1029-1032
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• 2008

Nowadays, the necessity of the NDT technique for concrete structure has been increased due to maintenance of infra-structure. With this reason, NDT detecting technique has been considered as a effective maintenance method to prevent the rapid degradation of the infra-structure. In this study, to investigate the internal defect of concrete structure, ultrasonic detection device and radar equipment was applied then tested in laboratory and field. In the result of the experimental test, the internal cavity and steel arrangement can be detected and it was possible to adopt the ultrasonic detection method to the maintenance of concrete structure. And an algorithm for performing the maintenance procedure of concrete structure applying ultrasonic detection device and radar equipment was developed and suggested in this study.

• Journal of the Korean Society for Nondestructive Testing
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• v.14 no.3
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• pp.172-176
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• 1994

Interpreted is the geometric signal in the angle beam ultrasonic testing for the pin-finger type of turbine blade roots. The geometry of the blade roots is described and the reflection conditions for appearance of the geometric signal are proposed. The general equation for its beam path is derived and verified. As the results, it is found that the geometric signal is the back reflection front the ligament edge, and its position and amplitude can be determined from the dimension of blade root and the beam directivity of transducer.

• Journal of the Korean Society for Nondestructive Testing
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• v.34 no.3
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• pp.254-259
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• 2014

A pressurized heavy water reactor (PHWR) core has 380 fuel channels contained and supported by a horizontal cylindrical vessel known as the calandria, whereas a pressurized water reactor (PWR) has only a single reactor vessel. The pressure tube, which is a pressure-retaining component, has a 103.4 mm inside diameter ${\times}$ 4.19 mm wall thickness, and is 6.36 m long, made of a zirconium alloy (Zr-2.5 wt% Nb). This provides support for the fuel while transporting the $D_2O$ heat-transfer fluid. The simple tubular geometry invites highly automated inspection, and good approach for all inspection. Similar to all nuclear heat-transfer pressure boundaries, the PHWR pressure tube requires a rigorous, periodic inspection to assess the reactor integrity in accordance with the Korea Nuclear Safety Committee law. Volumetric-based nondestructive evaluation (NDE) techniques utilizing ultrasonic and eddy current testing have been adopted for use in the periodic inspection of the fuel channel. The eddy current testing, as a supplemental NDE method to ultrasonic testing, is used to confirm the flaws primarily detected through ultrasonic testing, however, eddy current testing offers a significant advantage in that its ability to detect surface flaws is superior to that of ultrasonic testing. In this paper, effectiveness of flaw detection and the depth sizing capability by eddy current testing for the inside surface of a pressure tube, will be introduced. As a result of this examination, the ET technique is found to be useful only as a detection technique for defects because it can detect fine defects on the surface with high resolution. However, the ET technique is not recommended for use as a depth sizing method because it has a large degree of error for depth sizing.

• The Journal of the Acoustical Society of Korea
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• v.10 no.5
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• pp.46-50
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• 1991

고체내부에 존재하는 결함의 에이지에서 회절되는 반사신호의 스페그럼을 해석하여 결함의 크기 를 결정하는 방법을 연구하였다. 실험을 위하여 순도 99.99%의 알루미늄 재료를 샘플로서선택하고 표면 에서 20mm 깊이에 반경 3500μm, 높이 1000μm 의 동전형 결함을 제작하였다. 결함의 탐상은 피치-캐 치법으로 하였으며, 스펙트럼분석에 의한 결함의 기존의 펄스 반사법에 의한 측정값과 비교하였다.

• Transactions of the Korean Society of Automotive Engineers
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• v.12 no.2
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• pp.182-189
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• 2004

The application of adhesively bonded components is increasing in various industries such as automobile, aircraft, IC packages, and soldering techniques. In spite of such wide application in adhesively bonded components, nondestructive test techniques applying to adhesively bonded components have not been clearly established yet. In this paper, characteristics of ultrasonic test on interfaces of adhesively bonded components have been investigated by calculating transmission coefficient theoretically and experimentally. From the experimental results, the optimum conditions to establish frequencies for adhesively bonded homogeneous and dissimilar components are 4∼6 MHz and 2∼4 MHz, respectively.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05a
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• pp.557-562
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• 1997

노심용융물의 노내 자연 냉각 현상은 TMI-2 사고 이래로 실험과 해석 분야에서 많은 연구가 이루어지고 있으나, 아직까지는 이에 대한 명확한 규명이 이루어지지 않은 상태이다. 원자로 용기 냉각 Mechanism 중에서 노심용융물이 원자로 용기 하부 반구내로 재배치되어 하부 반구 내벽과 접촉할 때 용융물과 하부 반구 내벽 사이에 생길 수 있는 작은 간극으로 냉각수가 침투되어 노심용융물의 냉각이 이루어질 수 있다는 가정이 유력하게 제기되고 있다 본 논문에서는 노심용융물과 원자로 용기 하부 반구 사이의 간극을 통한 노심용융물의 냉각 특성을 규명하는 SONATA-IV실험 연구와 연계하여 이상 유동이 존재하는 고온 표면에서의 미세한 간극을 측정할 수 있는 방법의 검토 및 시편을 이용한 실험을 통하여 가장 적합한 간극측정기법을 도출하였다 간극 측정 기법으로는 중성자 래디오그라피, X 선 후방산란 단층기법 그리고 초음파 펄스 반사 탐상법을 검토하였으며, 시편 측정 실험결과 실시간 간극 측정방법으로는 초음파 펄스 반사 탐상법이 가장 적합한 것으로 나타났다.