• Journal of the Korean Society for Nondestructive Testing
• /
• v.28 no.5
• /
• pp.436-442
• /
• 2008

Graphite material has been recognized as a very competitive candidate for reflector, moderator, and structural material for very high temperature reactor (VHTR). Since VHTR is operated up to $900-950^{\circ}C$, small amount of impurity may accelerate the oxidation and degradation of carbon graphite, which results in increased porosity and lowered fracture toughness. In this study, ultrasonic wave propagation properties were investigated for both as-received and degradated material, and the feasibility of ultrasonic testing (UT) was estimated based on the result of ultrasonic property measurements. The ultrasonic properties of carbon graphite were half, more than 5 times, and 1/3 for velocity, attenuation, and signal-to-noise (S/N) ratio respectively. Degradation reduces the ultrasonic velocity slightly by 100 m/s, however the attenuation is about 2 times of as-receive state. The results of probability of detection (POD) estimation based on S/N ratio for side-drilled-hole (SDHs) of which depths were less than 100 mm were merely affected by oxidation and degradation. This result suggests that UT would be reliable method for nondestructive testing of carbon graphite material of which thickness is not over 100 mm. In accordance with the result produced by commercial automated ultrasonic testing (AUT) system, human error of ultrasonic testing is barely expected for the material of which thickness is not over 80 mm.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1998.05b
• /
• pp.851-856
• /
• 1998

국내에서 상업운전중인 월성 원자로는 캐나다에서 개발한 CANDU형 원자로로 핵연료를 지지하는 핵연료 압력관이 사용되며, 핵연료 압력관은 원자로의 1차기기로 건전성확보가 매우 중요하다. 가동중 검사시 압력관에서 결함이 검출되면, 지속적인 사용을 위해서 결함의 건전성을 확보하여야하나, 그 평가절차가 매우 복잡하다. 본 연구에서는 핵연료 압력관 평가를 보다 신속하고 효율적으로 수행하기 위한 건전성 평가시스템을 개발하였다. 개발된 평가시스템은 예리한 결함 및 둔한 함에 대한 평가를 수행할 수 있으며, 피로균열평가, 지체수소균열평가, 불안정파괴평가, 파단전누설평가, 소성붕괴평가모듈을 수록하고 있다. 또한 개발된 시스템을 검증하기 위하여 캐나다 ECL에서 제시한 평가결과와 비교함으로서 본 시스템의 효용성을 검증하였다.

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
• /
• 2012.04a
• /
• pp.745-745
• /
• 2012

원자력발전소에서 비상디젤발전기는 노심의 안전성을 지키는 매우 중요한 역할을 담당하고 있다. 이를 위해 디젤발전기는 신뢰성능 높게 유지하도록 규제요건이 마련되어 있다. 디젤발전기의 엔진 상태를 주기적으로 감시하고 평가하기 위해서는 엔진 상태 신호 분석 기술이 필요하다. 엔진 상태 신호 분석에는 연소분석과 진동 및 초음파 측정 및 분석기술이 중요한 비중을 차지한다. 연소 분석은 디젤 엔진의 개별 실린더에 대한 연소 성능에 대한 정보를 제공한다. 진동 및 초음파 분석은 이벤트 타이밍과 기계적 상태에 대한 정보를 알려준다. 이들 신호는 정상적인 부하로 운전하는 디젤엔진의 가동에 영향을 미치지 않고 수집할 수 있다. 엔진 상태 신호 분석을 이용하는 주요 동기는 전통적으로 장비 제작자의 권고에 따라 수행되는 분해-검사 유지 보수 프로그램을 일부 대체하고 예측정비를 통해 신뢰도를 유지하기 위함이다. 상태 진단정비는 엔진 상태 신호분석을 주로 이용하여 엔진의 신뢰도와 이용률을 증가시킬 수 있다. 본 논문에서는 국내외서 경험한 엔진상태신호 측정 및 분석 사례를 기술하였다.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1998.05a
• /
• pp.303-308
• /
• 1998

SMART 계측제어계통 측정신호의 신뢰성을 높이기 위한 실시간 신호검증알고리듬을 개발하였다. 개발된 알고리듬은 선행고장검출행렬, 아날로그 신호용 다중성 기법, 접촉신호용 논리표 알고리듬, 주파수 신호용 다중성 기법 그리고 아날로그 센서 경증을 위한 통계적 모듈의 5개 모듈로 구성되어 있다. 선행고장검출행렬은 측정 신호 중에서 고장의 가능성이 있는 신호를 추출하여 선정된 신호만을 적절한 알고리듬으로 검증하도록 함으로써 전체적인 수행시간을 감소시킨다. 아날로그 신호검증 모듈은 아날로그 측정신호에 대한 물리적/해석적 다중성에 입각하여 고장신호의 크기, 위치를 검출하며, 접촉신호 검증 모듈은 접촉신호들간의 논리값을 비교하여 발생 불가능한 논리값을 가지는 신호를 고장신호로 검출한다. 주파수신호는 아날로그 신호와 유사한 기법을 구현하였으며, 통계적 모듈은 아날로그 센서 자체의 물리적 건전성을 검사하는 모듈이다. 현재 SMART의 설계가 확정되어 있지 않으므로 개발된 신호검증알고리듬을 시험하기 위해서 여러 주요 공정변수가 표현되는 상용 원자로의 냉각재계통을 대상으로 검증 알고리듬을 구현하였으며, 운전모사기로 모사된 신호를 이용하여 개발된 신호검증알고리듬을 시험하였다. 시험결과 각 모듈별로 적절히 고장을 검출함을 보였다.

• Proceedings of the Computational Structural Engineering Institute Conference
• /
• 2010.04a
• /
• pp.696-699
• /
• 2010

원자력 발전소의 격납건물은 인위적 또는 자연적 재해로부터 방사능의 외부누출을 방지함으로써 공중을 보호하는 역할을 하기 때문에 지속적인 건전성 확인을 통해 안전을 확보하는 것이 필수적이다. 격납건물의 구조적 건전성 확인은 통상 주기적으로 콘크리트에 대한 비파괴강도, 균열 및 중성화, 프리스트레스 텐던의 유효 긴장력 등의 측정을 통해 수행되고 있으나, 이러한 검사는 국부적인 건전도 정보만을 제공할 뿐 격납건물과 같은 대형 구조물 전체의 건전성에 대한 신뢰성 있는 평가 결과를 얻는데 많은 시간과 경비가 소요된다는 단점이 있다. 이러한 단점은 최근 구조물 전체의 상태를 평가하는 방법으로 주목받고 있는 구조건전성모니터링(Structural Health Monitoring, SHM)기법을 이용하여 극복할 수 있다. 본 논문에서는 실제 운전 중인 격납건물을 대상으로 상시진동 측정을 수행하였으며, SHM 기법의 기초자료로 활용될 수 있는 동적특성, 즉 격납건물의 고유진동수와 모드형상을 제시하였다.

• Journal of the Korean Society for Nondestructive Testing
• /
• v.28 no.5
• /
• pp.407-415
• /
• 2008

The tubes in heat exchanger are typically made from copper alloy, stainless steel, carbon steel, titanium alloy material. type-439 ferritic stainless steel is ferromagnetic material, and furnish higher heat transfer rates than austenitic stainless steels and higher resistance to corrosion-induced flaws. Ferritic stainless steel can typically be found in low-pressure(LP) feedwater heaters and moisture separator reheaters(MSRs). LP feedwater heaters generally utilize thin wall type-439 stainless steel tubing, whereas MSRs typically employ a heavier wall tubing with integral fins. Service-induced damage can occur on the OD(outside diameter) surface of type-439 ferritic stainless steel tubing which is employed for MSRs tubing, and the most typical damage mechanism is vibration-induced tube-to-TSP(tube support plate) wear and fatigue cracking. The wear has been reported that occurs mainly on the OD surface. Accordingly, in this study, we have evaluated the flaw sizing capability of magnetic saturation eddy current technique using magnetic saturation probe and flawed specimen.

• Korean Chemical Engineering Research
• /
• v.58 no.3
• /
• pp.390-395
• /
• 2020

For some processes with saturations, economical operating points are on the saturation edges. Traditional feedback controllers cannot be used to regulate such processes on the saturation edges because there are abrupt dynamics changes and no feedback information at saturations. Optimization-based methods such as the model predictive control can treat this control problem without difficulty when the saturation levels and dynamics are known and not varying. Otherwise, an adaptation scheme to track the saturation levels and dynamics should be included. Here, for very simple methods to treat this control problem, two control methods based on the recent slope seeking method and the relay feedback method are proposed. Their performances are evaluated with simulations applying them to a second order liquid level system with saturation. Simulations show that these proposed control methods can find and maintain operating point of the saturation edge under 5% relative error.

• Journal of the Korean Institute of Gas
• /
• v.10 no.1 s.30
• /
• pp.32-37
• /
• 2006

Major components of refinery plants are exposed to various damage mechanisms depending on the operation condition, material selection and kinds of internal fluid. Inspection techniques and damage monitoring methods should be selected considering the damage mechanisms of the components. Hence, it is quite necessary to have an information system with a standardized database on the various damage mechanisms. In this study a damage information system with contents on the damage mechanisms included in API 571 code was developed. Concept of the screening table employed in USA and Japan was also adopted to identify the probable damage mechanisms from the information on operating temperature, internal fluid, metal used for the component and stress condition. This system can be used before the risk based inspection planning to identify key damage mechanisms involved.

• Journal of KSNVE
• /
• v.9 no.1
• /
• pp.85-96
• /
• 1999

For ASME Code pumps in nuclear power plants, inservice test is required to assess the operational readiness in accordance with ASME code and related regulations. The objective of this study therefore, is to develop the technical background of the degradation of pump performances and conditions due to low flow rate operation. In addition. the detection techniques of pump operating conditions are to be developed to enhance the safety and economy of nuclear power plants. A test loop consisted of pump, motor. water tank, flow rate measurements and piping system with flow control devices was established for this study. Two typical pumps, 1-stage volute pump and 3-stage turbine pump, were selected and the test was performed upon two major point of views ; i.e., pump discharge pressure pulsations analysis and pump vibration spectrum analysis. From the test results, it is concluded that (1) the pump vibration affected by the natural frequency of operating pump is significant in the low frequency zone (around 1 Hz) : the vibration amplitude. especially. is an important factor during low flow rate operation. and shall be monitored to ensure that it is within the limit of ASME OM code Part 6, (2) the vibration frequency and pump discharge pressure are affected by vane pass frequency and running speed, (3) the wave phenomena due to the compressiblity of water is anticipated during low flow rate operation. and the pump system shall be designed to prevent it and. finally, (4) the technical background of the degradation of pump performances and conditions due to low flow rate operation is provided.

• Journal of Korean Ophthalmic Optics Society
• /
• v.9 no.2
• /
• pp.473-480
• /
• 2004

Recently, they are interested in the relation between night's vehicle accidents of drivers and the dynamic visual acuity at home and aboard. So, in this research, we tried to design an optical system of the inspection equipment to measure the dynamic visual acuity. A optotype standard did to Landolt's ring with 45mm of diameter and 9mm of gap to maintain the visual acuity of 1.0 in the 30m distance. An optical structure of the inspection equipment was composed of the sequence of an observer, a plus refraction lens system, a minus refraction lens system, and an optotype that was arranged to have characteristics that the size of the first virtual image of the optotype made by the minus refraction lens system grows bigger gradually according to the optotype movement to near distance from far distance, and also the first virtual image moves to the principle plane from the focal point of the plus refraction lens system as the size of the first virtual image arranged to the inside of focal distance of plus refraction lens system grows bigger gradually. As doing these processes, we completed the optical system of which characteristic is that the position of the final second virtual image moves to 3m from 50m as the size of the second virtual image made by the plus refraction lens system maintains to be regular.