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RISS 인기검색어
- 검색키워드
- 저자 : 朴致承(C. S. Park) (검색결과 5 건)
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박광희,박종현,안희성,박치승 韓國非破壞檢査學會 1989 한국비파괴검사학회지 Vol.9 No.2
It has not been performed to inspect the underclad cracking in Korea nuclear plant since there is no Code Requirments for inspection. However, underclad cracks in nuclear pressure vessels were reported firstly in 1970. The objection of this study is to be established the ultrasonic inspection techniques for underclad cracking. The ultrasonic inspection of bimetalic stainless steel weld is very difficult by high attenuation and multiple scattering at weld surface and weld/base metal interface. The various inspection methods using 70。 refracted longitudinal wave. 50/70 tandem transducer, 45。 and 60。single shear wave are compared. Experiments on limited specimens applied same condition to nuclear pressure vessels shows that 70。refracted longitudinal wave method is the best one for the detection of underclad cracks. 50/70 tandem transducer using SPOT(Satellite Pulse Observation Technique) is more effective for underclad crack sizing than other sizing methods.
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Al材料에서 Ultrasonic Backscattered Energy와 Stress와의 相互關係
朴宗賢,朴致承,林亨澤 韓國非破壞檢査學會 1987 한국비파괴검사학회지 Vol.6 No.2
As a new device of stress monitoring method, ultrasonic backscattering method has been used to aluminium samples with various grain sizes at rayleigh critical angle in order to observe the relationships between applied stress and ultrasonic backscattered energy. It was found that the ultrasonic backscattered energy was observed to decrease as the grain size increased at the given applied stress. At the same grain size, the ule ultrasonic backscattered energy increased with increasing the applies stress. Through this study, we provided some possibility to evaluate stresses in materials under loads nonderstructively, and this method is expected to be used as a new stress monitoring device.
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허형,박치승,홍순신,박종현 韓國非破壞檢査學會 1989 한국비파괴검사학회지 Vol.9 No.1
Since the nuclear power plants in Korea have been operated in 1979, the nondestructive testing(NDT) of pressure vessels and/or piping welds plays an important role for maintaining the safety and integrity of the plants. Ultrasonic method is superior to the other NDT method in the viewpoint of the detectability of small flaw and accuracy to determine the locations, sizes, orientations, and shapes. As the service time of the nuclear power plants is increased, the radiation level from the components is getting higher. In order to get more quantitative and reliable results and secure the inspector from the exposure to high radiation level, automation of the ultrasonic equipments has been one of the important research and development(R & D) subject. In this research, it was attempted to visualize the shape of flaws presented inside the specimen using a Modified C-Scan technique. In order to develope Modified C-Scan technique, an automatic ultrasonic scanner and a module to control the scanner were designed and fabricated. IBM-PC/XT was interfaced to the module to control the scanner. Analog signals from the SONIC MARK II were digitized by Analog-Digital Converter(ADC 0800) for Modified C-Scan display. A computer program has been developed and has capability of automatic data acquisition and processing from the digital data, which consist of maximum amplitudes in each gate range and location. The data from Modified C-Scan results was compared with shape from artificial defects using the developed system. Focal length of focused transducer was measured. The automatic ultrasonic equipment developed through this study is essential for more accurate, reliable, and repeatable ultrasonic experiments. If the scanner are modified to meet to appropriate purpose, it can be applied to automation of ultrasonic examination of nuclear power plants and helpful to the research on ultrasonic characterization of the materials.
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선추적기법을 활용한 오스테나이트계 스텐레스강 용접부 초음파탐상 모의
임형택,김병철,박치승,이삼래 韓國非破壞檢査學會 1995 한국비파괴검사학회지 Vol.15 No.1
원자력 발전소의 주요 계통 재료로 사용되는 오스테나이트계 스텐레스강에 대한 초음파탐상은 초음파 에너지가 전파될 경우 재질 자체가 갖는 여러 문제점으로 인하여 결함 위치나 크기 측정에 많은 문제점을 야기한다. 본 연구에서는 이러한 문제점을 이해하기 위하여 여러가지 경우를 가정하여 선 추적(ray tracing) 기법을 사용한 컴퓨터 모의(simulation)를 실시하였다. 우선 종파를 사용하여 모재에 초음파가 입사하여 진행할 시 어느정도의 휘어짐이 발생하는지를 계산하였으며 재질 특성상 용접부와 모재가 큰 차이를 보이지 않는 경우와 원자로 노즐 부위와 같이 서로 다른 금속으로 용접된 경우에 결함이 존재한 경우를 가정하여 계산하였다. Crack detection technique by ultrasonics in structures and components made of austenitic stainless steel often loses its reliability due to the material characteristics during inservice inspection of nuclear power plants, expecially in the area of detection and sizing in centrifugally cast stainless steel pipings. In order to understand and overcome this problem, computer program for tracing the ultrasonic rays within material has been developed to simulate the process of defect detection within weld. The program simulates through transmission and reflection technique in crack detection of austenitic stainless steel as well as ultrasonic beam propagation through multiple media including stainless steel cladding interface.
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