• 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.

• Journal of the Korean Society for Nondestructive Testing
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• v.34 no.5
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• pp.384-389
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• 2014

In this paper, the result of an ultrasonic performance demonstration are analyzed. The requirements for an ultrasonic performance demonstration (PD) for a nuclear power plant were first described in ASME B&P Code Section XI, Appendix VIII (1989 winter addenda). In order to establish the performance demonstration scheme in Korean nuclear power plants, the Korea Hydro & Nuclear Power Co. Ltd (KHNP) has developed the Korean Performance Demonstration (KPD) system for the for the ultrasonic examination of nuclear power plants. An analysis of the ultrasonic performance demonstration results from 2004 through 2013 will improve the detection of flaws in an ultrasonic examination, as well as the further development of the KPD training system.

• Journal of the Korean Society for Nondestructive Testing
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• v.5 no.1
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• pp.34-47
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• 1985

The developing country, KOREA where does not possess the natural resources for traditional energy such as oil and gas, so. The nuclear energy is the most single reliable source available for closing the energy gap. For these reason, It is inavoidable to construct the nuclear power plant and to develop technology related nuclear energy. The rate of operation in large nuclear power facilities depends upon the performance of work system through design and construction, and also the applied technology. Especially, it is the most important element that safety and reliability in operation of nuclear power plant. In view of this aspects, Nuclear power plant is performed severe examinations during preservice and inservice inspection. This study provide an automation of analysis for volumetric examination which is required to nuclear power plant components. It is composed as follows: I. Introduction II. Inservice Inspection of Nuclear Power Plant ${\ast}$ General Requirement. ${\ast}$ Principle and Methods of Ultrasonic Test. ${\ast}$ Study of Flaw Evaluation and Design of Classifying Formula for Flaws. III. Design of Automation for Flaw Evaluation. IV. An Example V. Conclusion In this theory, It is classifying the flaws, the formula of classifying flaws and the design of automation that is the main important point. As motioned the above, Owing to such as automatic design, more time could be allocated to practical test than that of evaluation of defects, Protecting against subjective bias tester by himself and miscalculation by dint of various process of computation. For the more, adopting this method would be used to more retaining for many test data and comparative evaluating during successive inspection intervals. Inspite of limitation for testing method and required application to test components, it provide useful application to flow evaluation for volumetric examination. Owing to the characteristics of nuclear power plant that is highly skill intensive industry and has huze system, the more notice should be concentrated as follows. Establishing rational operation plan, developing various technology, and making the newly designed system for undeveloped sector.

• Journal of the Korean Society for Nondestructive Testing
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• v.24 no.4
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• pp.378-383
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• 2004

The Korean Performance Demonstration(KPD) System for the ultrasonic testing personnel, equipments and procedures applicable to the Class 1 and 2 piping examination for nuclear power plant in Korea has been established. A round robin test was conducted in order to compare the examination results by the method of Performance Demonstration(PD) with the traditional dB-drop method. The round robin test shows that the reliability of the PD method is better than that of the dB-drop method. As a result, adoption of the PD method to the in-service inspection of the nuclear power plants will improve the reliability of the ultrasonic test results.

• Journal of the Korean Society for Nondestructive Testing
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• v.18 no.3
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• pp.223-240
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• 1998

본 고는 1997년 12월 31일 개정된 "강 용접부의 방사선투과시험 방법 및 투과 사진의 등급분류 방법" (한국산업규격 KS B 0845)을 이해하는데 참고가 될 수 있도록 일본공업규격 JIS Z 3104의 해설부분을 번역한 것으로 KS B 0845의 모체가 되는 JIS Z 3104의 본래취지를 정확히 전달하기 위하여 편집하거나 가감하지 않고 원문 그대로 기술하였으며 KS B 0845와는 일부 용어나 항목구성에 차이가 있으나 번호에 관계없이 각항목의 제목을 보고 이해하게 하였다. 특히 일부 부속 규격의 미 제정상태에서 개정판이 발표되어 적용에 혼란을 초래할 수도 있겠으나 부분적인 적용은 가능할 것으로 판단된다.

• Journal of the Korean Society for Nondestructive Testing
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• v.11 no.1
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• pp.52-60
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• 1991

The importance and role of preservice and inservice inspection(PSI/ISI) for nuclear power plant components are intimately related to plant design, safety, reliability and operation etc.. The Korea Atomic Energy Research Institute(KAERI) has been performing PSI/ISI in Korea since the PSI of Kori nuclear power plant, unit 1 had been performed in 1977. KAERI has localized PSI/ISI technology and has done much experience in ultrasonic flaw detection, evaluation and its excavation on the weldments of large pressure vessels. The results of flaw estimation using ultrasonic examination are compared with the actual flaw sizes revealed by field excavation. KAERI's experience regarding PSI/ISI was described and some discussions were added.

• Journal of the Korean Society for Nondestructive Testing
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• v.13 no.2
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• pp.48-60
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• 1993

1974년에 유럽에서 시작된 PISC(Program for the Inspection of Steel Components ; PISC-I, II, III) 수행결과나 1980년대초 실시된 미국의 BWR 원전 배관계통의 입계응력부식균열(IGSCC ; Intergranular Stress Corrosion Cracks)검사결과에서 나타난 바와 같이 기존의 규격 요건과 절차에 따른 원자력발전소 기기에 대한 초음파탐상검사는 그 실효성에 많은 문제점이 제기되었다. 따라서, 원전기기의 건전성 및 초음파탐상검사 결과의 신뢰도를 보증하기 위한 각종 연구가 진행되고 여러 방안이 모색되어 왔다. 그 결과, 원전 가동중검사 규격에 "초음파탐상검사자 자격인정 요건"과 "초음파탐상검사 시스템(검사자, 장비 및 절차서)에 대한 기량검증 요건"이 새로이 부가되었다. 본고에서는 초음파탐상검사 결과의 신뢰도 확보에 있어 필수불가결한 요건인 원전기기 초음파 탐상검사 시스템에 대한 기량검증 요건을 자세히 기술한다.

• Journal of the Korean Society for Nondestructive Testing
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• v.14 no.1
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• pp.39-47
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• 1994

원자력발전소의 상온수압시험에는 여러가지 목적이 있으며 그 중에서 가장 중요한 것 중 하나는 원전 주요 기기로부터의 누설여부를 알아내는 것이다. 동 시험에서 누설 여부를 알아내기 위해 현재 국내에서는 미국 규격에 따라 육안검사를 수행하고 있으나 프랑스의 경우, 음향방출 누설시험과 육안검사를 수행토록 하고 있다. 저자는 1992년과 1993년 중국 광동 원전 1, 2호기의 가동전검사에 참여하여 프랑스의 RSEM 규격에 따라 실시된 상온수압시험시의 음향방출 누설시험과 누설 육안검사에 대하여 기술 지원 업무를 수행하였다. 동시험에서는 시험 최고 압력인 228bar에서는 음향방출 누설 감시시험과 누설 육안검사를, 감압단계인 155bar 에서는 누설 육안검사를 수행하였다. 본고에서는 동 규격에 따라 최초로 수행된 중국 광동 원전 가동전검사 수압시험시의 음향방출에 의한 누설감시와 누설 육안검사에 대해 검사 기술, 검사 방법, 검사 절차, 그리고 검사 대상부위 등을 기술하였다.

• Proceedings of the Korean Institute of Building Construction Conference
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• 2011.11a
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• pp.23-24
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• 2011

The purpose of this study is suggesting a basic data for which scientific preservation and rehabilitation of future modern architecture through the analyzing property of clay brick used in modern architecture in a scientific way.The clay brick which is used in the early 1900s has even lower property than present clay brick because of poor plasticity technique at that time. It could be possible to property and effective stability examination of modern architecture from nondestructive testing is significantly associated with property.

• Proceedings of the KSR Conference
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• 2007.05a
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• pp.1626-1630
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• 2007

This dissertation finds out trouble types and occurrence regions using the faulty statistics of nondestructive test items in rolling stock parts of the Seoul Metro and using mechanical test about defective and broken parts with broken surface observation, cutting examination about trouble region, hardness experiment and tensile test. Also this dissertation finds out cause of trouble and damage through observation of microscopic formation using metallurgical microscope and scanning electron microscope, residual stress measurement about welding parts and damage diagnosis about defective and broken parts. Moreover it will present the improved plan of nondestructive method about trouble and the removal method of defect and repair welding and find solutions of reliability in parts and preventive maintenance.