• 전력전자학회:학술대회논문집
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• 전력전자학회 2010년도 추계학술대회
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• pp.175-176
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• 2010

본 논문에서는 자기 베어링을 이용한 자기부상형 터보분자펌프 운용시 그 시스템에 공급되는 입력전원이 중단될 경우 모터의 발전 전압을 이용하여 일정시간동안 자기 베어링을 구동하여 분자펌프의 안정된 shut-down을 유도하도록 제어기에 전원을 공급하는 전원장치를 제안한다. 본 논문에서 제안한 전원장치는 300W급이며 입력전압 30~400V로 출력은 48V이다.

• 한국수소및신에너지학회논문집
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• 제30권3호
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• pp.243-250
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• 2019

In this study, to ensure the safety of the packaged hydrogen refueling system, the improvement plan was derived by using 3-dimensional CFD program (FLACS). We also confirmed the effectiveness of risk reduction and the suitability of safety standard. By ventilation performance evaluation according to the position of the vent, it demonstrated that the vent should be installed at the ceiling to safely ventilate without stagnation of the leaked gas. In case of ventilation system according to KGS standard, risk situation could be resolved after about 5 minutes in the worst leaked condition. The result showed that jet fire and explosion inside the packaged system could affect the surrounding facilities. This proves that the standard for installing flame detectors, emergency shut down system and protection wall is appropriate.

• 한국초전도저온공학회:학술대회논문집
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• 한국초전도저온공학회 2002년도 학술대회 논문집
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• pp.285-290
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• 2002

Power systems are becoming larger and larger for meeting electric power demand. Therefore, the over-currents resulting from contingencies such short circuits are increasing higher. The Maximum short circuit current of modern power system is becoming so large that circuit breaker are not expected th be able to shut down the current in the future. In order to cut over-currents, a system composed of a superconducting fault current limiter(SFCL) and traditional breaker seems to provide a promising solution for future power operation. In present paper, three line-to-ground fault is assumed to happen at the center of 345kV transmission lines in a large capacity electric power system The superconducting fault current limiter was represented using a commutation type, which consists of a non-inductive superconducting coil and current limiting element(resistor or reactor). The introduction merits of the SFCL were investigated quantitatively by RTDS/EMTDC from the viewpoint of current limiting performance, the prevention of the voltage drop at the load bus and comparison characteristics for two type SFCL. Desired design specification and operation parameters of SFCL were also given qualitatively by the performance evaluation of the two type SFCL in the power system.

• 조명전기설비학회논문지
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• 제28권2호
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• pp.92-99
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• 2014

The paper is related to smart maximum power system based on program logic. Especially, this system compares the total demand power with the target power by using the signal from the digital kilo watt meter. Based on the power information by the maximum power control equipment the consumed future power is anticipated. In addition, through consumed future power the controllable target power is set, and it applies on the maximum power control equipment. User or manager would control the load efficiently through the simple programming which could control load based on the control sequence and relay. To begin with the conventional maximum power control algorithm is surveyed, and the smart maximum power control system based on program logic is used, and the new algorithm from full load to proportion shut down is proposed by using PLC program. the validity of the proposed control scheme is investigated by both simulation results.

• 융합신호처리학회논문지
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• 제5권1호
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• pp.60-65
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• 2004

고주파 유도 가열 시스템에서 철과 같은 물체를 가열하게 되면, 가열된 금속이 큐리점 부근에서 전기적인 임피던스가 급격하게 변화하는 특징을 가지는 시변 시스템이 된다. 또한 부하 임피던스가 변화함에 따라 시스템의 부하 공진 주파수가 달라지므로 해서 시스템의 효율이 감소하는 문제점이 있었다. 그리고, 피가열 물체의 용융이나 삽입 상태에 따른 시스템의 단락 현상으로 인해 시스템이 파괴되는 문제점이 있었다. 본 논문에서는 이런 문제점을 해결하기 위한 방법으로 PLL에 의한 부하 공진 주파수를 추종하면서 스위칭 손실을 줄이고, 시변 부하에 대한 유도 가열시 큐리점 부근의 급격한 부하 임피던스 변화에도 안정된 정전력 제어가 가능할 뿐 아니라 대전력용에 적합하고, 단락현상으로부터 시스템을 보호하는 병렬 공진형 인버터 시스템에 적용되는 퍼지논리 제어기를 설계하였다.

• 방사성폐기물학회지
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• 제14권3호
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• pp.289-295
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• 2016

국내 최초로 건설된 가압경수로형 발전소인 고리1호기는 1978년 4월 첫 상업운전을 개시하였고, 2017년 6월 18일 영구정지 될 계획이다. 고리1호기에서는 사용후핵연료가 사용후핵연료저장조로 모두 이송된 이후, 계통 표면의 선량율을 감소시키기 위한 목적으로 전계통 제염을 실시할 계획이다. 이 논문에서는 해외 원전의 계통제염 사례분석을 통해 국내 최초로 시행될 예정인 고리1호기의 계통제염 운전개념을 기술하고자 하였다.

• 한국압력기기공학회 논문집
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• 제16권1호
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• pp.22-29
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• 2020

In nuclear power plants, there is a risk of thermal fatigue in equipment and piping affecting system soundness because the temperature change of the system accompanies in every operation and shutdown. Therefore, in order to prevent the excess of the fatigue limit during the lifetime of plants, the fatigue limit of each piping material is determined in the designing stage. However, there are many cases where equipment or piping is locally subjected to thermal fatigue that is not considered in the design, resulting in damage to the equipment and piping, and failure during operation. Currently, local thermal fatigue generation mechanisms that are not taken into account in the design stage are gradually being identified. In this paper, the effects of the fluid temperature fluctuations on the piping soundness due to the mixing of hot and cold water, one of the local thermal fatigue generating mechanisms, were evaluated.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 학술논문집
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• pp.58-71
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• 2004

연구용원자로를 해체하는 과정에서 발생되는 각종 자료들은 여러 장소에서 상호 호환성 없는 형태로 발생하므로 관리와 활용이 용이하지 않다. 연구로 1, 2호기를 해체하면서 발생되는 자료를 해체시설, 해체작업, 방사선학적 그리고 해체폐기물 정보영역별로 분류하여 자료를 관리하고 보다 객관적이고 정확한 정보 분석이 가능하도록 데이터베이스 시스템을 개발하였다. 연구용 원자로 해체활동 자료에 대한 체계가 구축됨으로써 해체사업을 보다 더 효율적으로 수행하는 데 도구로 활용할 수 있을 것이다. 해체 현장 자료 입력, 분석 및 평가를 통하여 연구로 1, 2호기 해체활동 자료에 대하여 보다 객관적이고 정확한 평가가 가능하게 되었고, 이를 바탕으로 연구로 1, 2호기 해체프로젝트를 보다 효율적으로 수행할 수 있게 될 것이다.

• 한국공작기계학회논문집
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• 제17권6호
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• pp.43-48
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• 2008

This study includes contents on an effective designing of the outer-wall piece removing equipment of a hull, by applying TRIZ. To remove the piece, gas torch was used. However, the heat source must be shut down since the heat source of gas torch has a bad influence on this system. This is why TRIZ and Brainstorming were used, to solve this problem. First, we analyzed the system using TRIZ, and then presented the direction a solution is expected to follow. And the most suitable scheme was derived from brainstorming which had been conducted based on the direction of a solution. Lastly we conducted an equipment modeling based on the most suitable scheme we made before, and carried out the heat analysis to inspect its effect by comparing pre-existing mechanism with most suited scheme.

• Nuclear Engineering and Technology
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• 제41권1호
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• pp.91-98
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• 2009

The "3+3 Process" for safety critical software for nuclear power plants' I&C (Instrumentation and Control system) has been developed in this work. The main idea of the "3+3 Process" is both to simplify the software development and safety analysis in three steps to fulfill the requirements of a software safety plan [1]. The "3-Step" software development process consists of formal modeling and simulation, automated code generation and coverage analysis between the model and the generated source codes. The "3-Step" safety analysis consists of HAZOP (hazard and operability analysis), FTA (fault tree analysis), and DV (design validation). Put together, these steps are called the "3+3 Process". This scheme of development and safety analysis minimizes the V&V work while increasing the safety and reliability of the software product. For assessment of this process, validation has been done through prototyping of the SDS (safety shut-down system) #1 for PHWR (Pressurized Heavy Water Reactor).