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RISS 인기검색어
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- 저자 : 서정관(Jeong-Kwan Suh) (검색결과 4 건)
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500MW급 표준화력발전소 시뮬레이터 모델을 이용한 디지털 제어시스템 검증
서정관,이명수,홍진혁,Suh, Jeong-Kwan,Lee, Myeong-Soo,Hong, Jin-Hyuk 한국시뮬레이션학회 2010 한국시뮬레이션학회 논문지 Vol.19 No.3
The simulator models for 500MW fossil power plant have been developed, and interconnected with the turbine control system to test and validate the digital instrumentation & control (I&C) systems before they are implemented in operating power plants. When the performance of a selected digital I&C system is tested, the corresponding simulator model is replaced by the plant digital I&C systems which is considered as a non-tunable system. The input/out variables of simulator models and control systems were mapped using the LabView in interface systems. This paper describes the interconnection method between the simulator model and the digital I&C system, and summarizes the validation test results performed at the condition of steady-state operation, normal evolution, and malfunction. The integrated validation method of digital I&C systems using the simulator models showed that the simulator can be used as a test bed for the implementation of digital I&C systems in power plants.
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APR1400 노내하류효과 시험장치 관내 유동안정기 설치 형상에 따른 내부유동 해석
권순국(Sun-Guk Kwon),김재원,서정관(Jeong-Kwan Suh) 대한기계학회 2014 대한기계학회 춘추학술대회 Vol.2014 No.11
Flow analyses were performed to investigate the effects of flow straightener geometry on the uniformity of internal flow by changing the number of holes for a APR1400 Downstream Effect Test Facility. The flow straightening device is installed in the inlet of fuel assembly(FA) test column. In order to uniformly build up of debris in FA test column, the uniformity of internal flow is important. In this study, the flow straightener 8×8 and 9×9 hole were adopted to evaluate flow velocity characteristics. Calculated velocity distributions at the inlet of the FA test column were compared with the condition without flow straightener.
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신혜영(Hye-Young Shin),양원석(Won-Seok Yang),서정관(Jeong-Kwan Suh) 한국비파괴검사학회 2018 한국비파괴검사학회지 Vol.38 No.4
원자력발전 기술은 후쿠시마 원전 사고 발생에도 불구하고 가속화되는 지구온난화에 대처하고 인류의 지속적인 에너지 니즈에 대응하기 위한 최선의 검증된 실용 기술로 받아들여지고 있다. 따라서 노후 원전을 대체해야 하는 원자력 선진국과 새로운 발전원으로 삼고자 하는 신규 원전 도입국의 원전 건설 수요는 당분간 지속될 것으로 기대된다. 우리나라는 90년대부터 원전기술자립을 추진한 결과 2009년 12월 APR1400 4기를 최초로 UAE에 해외 수출한 이래 40년간의 안정적인 원전 건설/운영 경험을 바탕으로 신규 수요가 예상되는 유럽 등 해외시장에서의 원전 건설 수주 확대를 도모하고 있다. APR1400 기반 설계 기술은 2017년 유럽사업자요건(EUR) 부합성 인증서를 취득한 바 있으나 유럽 원전 수주 시장에서의 경쟁력을 제고하고 실질적인 건설에 대비하기 위해서는 설계뿐 아니라 기기 제작 및 건설관련 유럽형 코드 및 기술기준과의 부합성을 설계단계에 미리 확보해야할 것이다. 본 연구에서는 ENIQ 방법에 기초한 유럽형 비파괴검증 기술을 고찰하고 해외 경쟁노형의 적용사례를 조사/검토함으로써 우리나라 수출형 원전의 유럽시장 진출을 위한 비파괴검증기술 분야의 대응 전략 및 방안을 제시하고자 한다. Nuclear power generation technology is still being considered, in spite of the Fukushima accident, as the best realistic energy solution to cope with the global warming crisis and respond to the increasing global demand for energy consumption. Therefore, there is need for additional nuclear power plant (NPP) construction, which is expected to continue increasing. Since the first export of APR1400 to the UAE in a continuing effort to achieve nuclear technology self-confidence, Korea has been considering additional exports of APR1400 to the global NPP market. APR1400 is a design based technology that has successfully completed the assessment process and finally acquired EUR Certification in 2017; however, obtaining compatibility with European code and standards for components manufacturing and construction is essential for competition in the European market. This study reviews the European non-destructive examination inspection qualification technology based on ENIQ methodology, compares this process with domestic practices, investigates cases for other competitive reactors, and finally identifies considerations and strategies to obtain better confidence on inspection quality of APR1400.
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김재원(Jae-Won Kim),권순국(Sun-Guk Kwon),서정관(Jeong-Kwan Suh) 대한기계학회 2014 대한기계학회 춘추학술대회 Vol.2014 No.11
Debris occurred after a loss of coolant accident in nuclear power plants could be introduced into the reactor core during the recirculation phase. Debris in the recirculating coolant could accumulate on the bottom nozzle and the fuel rod surface of fuel assembly(FA). It could be caused differential pressure through the fuel assembly. Debris could increase differential pressure of fuel assembly as a flow resistance. We has performed in-vessel downstream effect tests for simulating this phenomena using PLUS7 mock up FA which is for the APR1400. Debris for the test are comprised of fibrous, particulate and chemical. In this study we aimed chemical mixing with water. It is necessary to maintain chemical mixing module with homogeneous state. In this study, Fluid behavior analysis was carried out in the debris mixing module according to the Impeller position for efficient mixing using computational fluid dynamics(CFD).
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