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RISS 인기검색어
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- 저자 : 성제중 ( Je Joong Sung ) (검색결과 7 건)
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총채널 불확실도를 적용한 원전 노심출구온도의 운전가능 판정기준
성제중 ( Je Joong Sung ),윤덕주 ( Yoon Duk Joo ),하상준 ( Sang Jun Ha ) 한국안전학회(구 한국산업안전학회) 2014 한국안전학회지 Vol.29 No.6
Nuclear power plants are equipped with the reactor trip system (RTS) and the engineered safety features actuation system(ESFAS) to improve safety on the normal operation. In the event of the design basis accident (DBA), a various of post accident monitor(PAM)systems support to provide important details (e.g. Containment pressure, temperature and pressure of reactor cooling system and core exit temperature) to determine action of main control room (MCR). Operator should be immediately activated for the accident mitigation with the information. Especially, core exit temperature is a critical parameter because the operating mode converts from normal mode to emergency mode when the temperature of core exit reaches 649 ℃. In this study, uncertainty which was caused by exterior environment, characteristic of thermocouple/connector and accuracy of calibrator/indicator was evaluated in accordance with ANSI-ISA 67.04. The square root of the sum of square (SRSS) methodology for combining uncertainty terms that are random and independent was used in the synthesis. Every uncertainty that may exist in the hardware which is used to measure the core exittemperature was conservatively applied and the associative relation between the elements of uncertainty was considered simultaneously. As a result of uncertainty evaluation, the channel statistical allowance (CSA) of single channel of core exit temperature was+1.042%Span. The range of uncertainty,-0.35%Span (-4.05℃) ~ +2.08%Span(24.25℃), was obtained as the operating criteria of core exit temperature.
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성제중(Sung Je Joong) 대한기계학회 2014 대한기계학회 춘추학술대회 Vol.2014 No.11
Nuclear power plants are equipped with post accident monitor (PAM) system to acquire the important parameters for safety operating. In the event of the design basis accident (DBA), PAM provides important details (e.g. Containment pressure, temperature and pressure of reactor cooling system and core exit temperature) to determine action of main control room (MCR). Operator should be immediately activated for the accident mitigation with the information. Especially, core exit temperature is a critical parameter because the operating mode converts from normal mode to emergency mode when the temperature of core exit reaches 649℃. In this study, uncertainties which were caused by exterior environment, characteristic of thermocouple/connector and accuracy of calibrator/indicator were evaluated in accordance with ANSI-ISA 67.04. The square root of the sum of square (SRSS) method was used in the synthesis. Every uncertainty that may exist in the hardware which is used to measure the core exit temperature was conservatively applied and the associative relation between the elements of uncertainty was considered simultaneously. As a result of uncertainty evaluation, the channel statistical allowance (CSA) of single channel of core exit temperature was +1.042%Span. The range of uncertainty, ?0.35%Span (?4.05℃)~ +2.08%Span(24.25℃), was obtained as the operating criteria of core exit temperature.
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성제중,서동만,신용훈,엄태건,서동섭 한국비파괴검사학회 2003 학술대회 논문집 Vol.- No.1
Ferromagnetic material like the steel tubes can easily distort eddy current testing signal due to increased magnetic permeability for defects. Because magnetic field of the test probe is affected in an inconsistent way when the material under the testing has permeability. This permeability effect can be reduced by magnetic saturation. In this paper eddy current testing system was developed to detect flaws on the steel tubes. Magnetic saturation probe with helmholtz coil was designed for saturation and inspection of the steel tubes. When using the designed test probe, the relationship between flaw signals and noises was obviously discriminated. Additionally, a high pass filter was included in the eddy current board to minimize noises due to DC magnetic field.
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권정현,장홍래,성제중,안형근,장순재,송문호 한국비파괴검사학회 2003 학술대회 논문집 Vol.- No.1
The nondestructive testing using ultrasonic pulse-echo data is an effective test methodology esperially for metal structure. Typically, the ultrasonic pulse-echo data is processed and the results are shown in A-scan, B-scan or C-scan formats. Upon viewing B-scan and C-scan data the viewer is able to identify the location of faults as well as their rough dimension. In this paper, we evaluate the applicability of various 3-D visualization methods frequently used in medical imaging, namely, surface rendering (SR), volume rendering (VR) and maximum intensity projection (MIP), for nondestructive testing purposes. Such 3-D visualization of ultrasonic pulse-echo data enables easier identification of the location and dimension of faults more accurately.
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송문호,손상락,조정호,성제중,안형근,장순재 한국비파괴검사학회 2003 한국비파괴검사학회지 Vol.23 No.5
비파괴 시험을 위한 3차원 구조의 초음파 영상에는 다양한 결함을 명백하게 보여줄 수 있을 만큼 상세하고 쉽게 알아볼 수 있는 정보가 제공되어야 한다. 수년 동안 원자력 발전소에서 사용된 금속관에 발견되는 소규모의 균열은 전형적인 결함들인데, 이러한 밀리미터 이하의 균열이나 결함은 최종 3차원 영상에서 묘사되어야만 의미있는 검사가 될 것이다. 향상된 선명도와 그에 따른 결함의 발견 과정의 한 단계로써, 펄스에코(pulse-echo) 초음파를 사용한 3차원 영상제작 기술을 제안한다. 이 기술은 필요한 스캐닝과 펄스에코 데이터의 처리과정을 통한 검사로 3차원 물체의 3차원 영상을 생성하는데, 2차원 위너필터(Wiener filter)에 의해 초음파 빔을 선명하게 하는 기술을 포함한다. 제안하는 위너필터는 빔의 전달에서 펄스에코 데이터를 초음파 빔 방향의 수직방향에 따라 필터링한다. 이 3차윈 처리과정은 결함의 선명성을 증진시키고 사용자에게 3차윈 구조물의 좌우 회전 및 축 회전과 같은 조작 능력을 제공한다. 이러한 조작 능력은 3차원에서 다양한 결함들의 크기와 위치의 분명한 묘사를 가능하게 한다. Infrasonic imaging of 3-D structures for nondestructive evaluation must provide readily recognizable images with enough details to clearly show various flaws that may or may not be present. Typical flaws that need to be detected are miniature cracks, for instance, in metal pipes having aged over years of operation in nuclear power plants; and these sub-millimeter cracks or flaws must be depicted in the final 3-D image for a meaningful evaluation. As a step towards improving conspicuity and thus detection of flaws, we propose a pulse-echo ultrasonic imaging technique to generate various 3-D views of the 3-D object under evaluation through strategic scanning and processing of the pulse-echo data. We employ a 2-D Wiener filter that filters the pulse-echo data along the plane orthogonal to the beam propagation so that ultrasonic beams can be sharpened. This three-dimensional processing and display coupled with 3-D manipulation capabilities by which users are able to pan and rotate the 3-D structure improve conspicuity of flaws. Providing such manipulation operations allow a clear depiction of the size and the location of various flaws in 3-D.
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