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김회웅,주영상,이영규,박상진,구경회,김종범,김성균,Kim, Hoe Woong,Joo, Young Sang,Lee, Young Kyu,Park, Sang Jin,Koo, Gyeong Hoi,Kim, Jong Bum,Kim, Sung Kyun 한국압력기기공학회 2016 한국압력기기공학회 논문집 Vol.12 No.1
Since the sodium-cooled fast reactor is operated in a hostile environment due to the use of liquid sodium as its coolant, advanced techniques for in-service inspection are required to periodically verify the integrity of the reactor. This paper presents the development of in-service inspection techniques for Proto-type Generation IV Sodium-cooled Fast Reactor. First, the 10 m long plate-type ultrasonic waveguide sensor has been developed for in-service inspection of reactor internals, and its feasibility was verified through several under-water and under-sodium experiments. Second, the combined inspection system for in-service inspection of ferromagnetic steam generator tubes has been developed. The remote field eddy current testing and magnetic flux leakage testing can be conducted simultaneously by using the developed inspection system, and the detectability was demonstrated through several damage detection experiments. Finally, the electro-magnetic acoustic transducer which can withstand high temperature and be installable in the remote operated vehicle has been developed for in-service inspection of the reactor vessel, and its detectability was investigated through damage detection experiments.
소듐냉각고속로 원자로용기 가동중검사를 위한 고온 전자기음향 트랜스듀서 개발
김회웅(Hoe-Woong Kim),박상진(Sang-Jin Park),손진관(Jin-Gwan Son),주영상(Young-Sang Joo),김성균(Sung-Kyun Kim),김종범(Jong-Bum Kim) 한국비파괴검사학회 2018 한국비파괴검사학회지 Vol.38 No.4
액체 금속인 소듐을 냉각재로 사용하는 제 4세대 원자로인 소듐냉각고속로의 원자로용기는 가동중 검사 기간에도 소듐의 고화를 방지하기 위해 200°C 정도의 고온 상태로 유지되어야 하고, 소듐-물 반응을 배제하기 위해 검사 시 액체 접촉 매질의 사용이 제한되어 있다. 또한, 원자로용기를 둘러싸고 있는 격납용기와의 간격이 협소하여 직접적인 접근이 어렵기 때문에 원격제어장비를 사용하여 검사를 수행하여야 한다. 이와 같은 가혹한 조건 하에서 원자로용기의 가동중검사를 수행하기 위해 본 연구에서는 원격제어장비에 탑재가 가능한 고온 전자기음향 트랜스듀서를 개발하였다. 먼저, 개발된 고온 전자기음향 트랜스듀서의 방사패턴과 리프트 오프에 따른 신호대잡음비 변화를 측정하여 개발된 트랜스듀서의 특성을 분석하였고, 내부 결함이 모사된 원자로용기 시편에 대한 결함 탐지능 측정시험과 내열성 시험 및 내구성 시험을 수행하여 고온 환경에서의 적용 가능성을 평가하였다. The reactor vessel in a sodium-cooled fast reactor, a generation-IV reactor, is in a high-temperature condition (approximately 200°C) even during the in-service inspection period and the liquid couplant, which is necessary for contact ultrasonic examination, is not permitted to be applied for the inspection to prevent sodiumwater reaction. Moreover, the remotely operated vehicle should be employed for inspection in the narrow gap between the reactor vessel and the containment vessel. For the in-service inspection of the reactor vessel under such harsh conditions, a high-temperature electro-magnetic acoustic transducer installable in the remotely operated vehicle was developed in this study. First, the radiation pattern and the signal-to-noise ratio according to the lift-off variation were investigated to analyze the characteristics of the developed transducer. Furthermore, the detectability, heat resistance, and durability of the developed transducer were then evaluated to demonstrate its applicability.
배관에서의 특정 비틀림 초음파 모드 송수신을 위한 합성 위상 조절 기법
김회웅(Kim, Hoe Woong),권영의(Kwon, Young Eui),주영상(Joo, Young Sang),김종범(Kim, Jong Bum),김윤영(Kim, Yoon Young) 한국소음진동공학회 2013 한국소음진동공학회 논문집 Vol.23 No.3
This study newly presents a synthetic phase tuning technique to suppress the unwanted torsional mode while enhancing the desired torsional mode in a pipe. Specifically, we aim at the enhancement of the first torsional mode and the suppression of the undesired, second torsional mode. Earlier efforts were to enhance the desired wave mode only in the hope that the enhancement results in the suppression of the unwanted wave mode. Unlike these efforts, the suggested technique makes the complete cancellation of the unwanted wave mode but it is shown to enhance the desired first mode for torsional wave problems. In the present study, the synthetic phase tuning is developed for the cancellation of the unwanted wave mode, meaning that the number of necessary experimental equipments is reduced. Simulation and experiment were carried out to check the effectiveness of the proposed method. As an application of the suggested technique, we investigated the reflection and mode conversion characteristics of the first torsional mode according to the step thickness variation in a stepped pipe.
김영태,김회웅,정문호 한국노인복지학회 2010 노인복지연구 Vol.0 No.50
Long-term care service for the elderly started in 2008 and it had shown so much achievement despite its new. This study attempted to find the problem on human management focused on care giver at long-term care center among long-term care insurance system. For the purpose of this study, it surveyed to target care givers working at the Seoul and Keonggido as the self administered questionnaire. Surveyed date analyzed through SPSS. This study obtained the following results:First, human management degree at long-term care center have generally level of ordinary status except level of income and proper number of workers. Second, care givers think that license for care giver is a big problem specially in terms of inappropriate educational period and unsuitable education center. Third, care giver organization owned by local government and Welfare Corporation are more satisfactory rather than those at private center in selection and contribution areas. Forth, care giver who worked less than 1year are more satisfactory rather than those who worked more than 1year at long term care center in compensation and education areas. Fifth, care givers who worked at urban areas have more contentment rather than those who worked at rural areas in education and compensation areas. Sixth, care givers who worked at established long-term care centers after 2008 have more contentment rather than that of those who worked before 2007. 본 연구는 노인요양시설의 요양보호사 인력관리에 관한 연구이다. 본 연구는 요양시설에서 근무하고 있는 요양보호사들의 시설 내 인력관리에 대한 인식을 통해 문제점을 도출해보고 개선방안을 찾아보는데 있다. 본 연구는 목적달성을 위해 서울 및 경기지역의 노인요양시설에 근무하는 요양보호사를 중심으로 자기기입방식에 의한 설문조사를 실시하였다. 조사된 자료는 통계 package인 SPSS를 사용하여 분석하였으며, 다음과 같은 결과를 얻었다. 첫째, 전체적으로 노인요양시설의 인력관리수준은 보통정도를 보였으나, 임금수준 및 인력의 적정성은 낮은 수준을 보였다. 둘째, 요양보호사 자격제도가 실무에서 적절한가에 대한 부문에는 교육기관의 난립과 교육기간의 부적절성으로 인해 적절하지 않다는 응답이 높았다. 셋째, 사회복지법인과 지방자치단체에서 운영하는 기관의 요양보호사에 대한 선발과 업적에 대한 인식이 개인이 하는 시설에 비해 좋게 나타났다. 넷째, 근무기간은 1년 미만인 경우가 1년 이상인 경우에 비해 요양보호사의 교육과 보상에 대한 인식이 좋았다. 다섯째, 도심지역과 교외지역에 근무하는 요양보호사의 교육과 보상에 대한 인식이 농촌지역에 비해 좋게 나타났다. 여섯째, 2008년 이후에 설립된 기관에서 근무하는 요양보호사의 교육과 보상에 대한 인식이 2007년 이전에 설립된 기관에서 근무하는 요양보호사에 비해 교육과 보상에 대해 보다 좋은 인식을 보였다.
이영규,김회웅,이재한,구경회,김종범,김성균,Lee, Young Kyu,Kim, Hoe Woong,Lee, Jae Han,Koo, Gyeong Hoi,Kim, Jong Bum,Kim, Sung Kyun 한국압력기기공학회 2016 한국압력기기공학회 논문집 Vol.12 No.1
The Control Rod Assembly (CRA) controls the reactor power by adjusting its position in the reactor core during normal operation and should be quickly inserted into the reactor core by free drop under scram condition to shut down chain reactions. Therefore, the drop time of the CRA is one of important factors for the safety of the nuclear reactor and must be experimentally verified. This study presents the drop performance test of the CRA which has been conceptually designed for the Proto-type Generation IV Sodium-cooled Fast Reactor. During the test, the CRA was free dropped from a height of 1 m under different flow rate conditions and its drop time was measured. The results showed that the drop time of the CRA increased as the flow rate increased; the average drop times of the CRA were approximately 1.527 seconds, 1.599 seconds and 1.676 seconds at 0%, 100% and 200% of design flow rates, respectively.
이영규,이재한,김회웅,김성균,김종범 한국원자력학회 2017 Nuclear Engineering and Technology Vol.49 No.4
The control rod assembly controls reactor power by adjusting its position during normaloperation and shuts down chain reactions by its free drop under scram conditions. Therefore, the drop performance of the control rod assembly is important for the safety ofa nuclear reactor. In this study, the drop performance of the conceptually designed controlrod assembly for the prototype generation IV sodium-cooled fast reactor that is beingdeveloped at the Korea Atomic Energy Research Institute as a next-generation nuclearreactor was experimentally investigated. For the performance test, the test facility and testprocedure were established first, and several free drop performance tests of the control rodassembly under different flow rate conditions were then carried out. Moreover, performancetests under several types and magnitudes of seismic loading conditions were alsoconducted to investigate the effects of seismic loading on the drop performance of thecontrol rod assembly. The drop time of the conceptually designed control rod assembly for0% of the tentatively designed flow rate was measured to be 1.527 seconds, and this agreeswell with the analytically calculated drop time. It was also observed that the effect ofseismic loading on the drop time was not significant.