• 대한전기학회:학술대회논문집
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• 대한전기학회 1992년도 하계학술대회 논문집 A
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• pp.126-129
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• 1992

Compared to other sources of electricity such as Thermal and Nuclear power plant, dispersed storage and generation system (DSG) is environmentally clean, quiet and efficient, thus this source is expected to be introduced In urban area by the utilities and customers. If a great number of DSG will be applied to electric power system in the rear future (around 2000, in Korea), these will give a great influence on the existing power system. In other words, the interconnection to electric power system of these source may bring many problems such as system operation, protection coordination, and service quality related with voltages (110${\pm}$6V, 220${\pm}$13V), harmonics (5%) and pour factor (90% over). So, this analysis of the interconnection to power system of DSG is required

• 시스템엔지니어링학술지
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• 제15권1호
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• pp.1-8
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• 2019

Reverse engineering involves examining a system or component so as to comprehend its structure, functionality, and operation. Creation of a system model in reverse engineering can serve several purposes: test generation, change impact analysis, and the creation of a new or modified system. When attempting to reverse engineering a system, often the most readily accessible information is the system description, which does not readily lend itself to use in Model Based System Engineering (MBSE). Therefore, it is necessary to be able to transform this description into a diagram, which clearly depicts the behavior of the system as well as the interaction between components. This study demonstrates how sequence diagrams can be extracted from the systems description. Using MBSE software, the sequence diagrams for the Engineered Safety Features Component Control System (ESF-CCS) of the Nuclear Power Plant are created. Sequence diagrams are chosen because they are a means of representing the systems behavior and the interaction between components. In addition, from these diagrams, the system's functional requirements can be elicited. These diagrams then serve as the baseline of the reverse engineering process and multiple system views are subsequently be created from them, thus speeding up the development process. In addition, the use of MBSE ensures that any additional information obtained from auxiliary sources can then be input into the system model, ensuring data consistency.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2002년도 하계학술대회 논문집 D
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• pp.2212-2215
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• 2002

This dissertation suggests and implements a middle level network which is called PICNET-NP (Plant Implementation and Control Network for Nuclear Power Plant). PICNET-NP is based partly on IEEE 802.4 token-passing bus access method and partly on IEEE 802.3 physical layer. For this purpose a new interface a physical layer service translator, is introduced. A control network using this method is implemented and applied to a distributed real-time system. To verify the performance of proposed protocol experimental were carried out, and the following results are obtained. 1) proper initialization of the protocol. 2) normal receiving and transmission of data. 3) proper switching of transmission media in case of a fault condition on the one of transmission media. The proposed protocol exhibits the excellent performance in the experimental system. From the test results in the experimental system, the proposed protocol, PICNET-NP, can be used for the upgrading of a nuclear power plant and the distributed control system in the next generation of nuclear power plant.

• Journal of Electrical Engineering and Technology
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• 제5권1호
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• pp.16-20
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• 2010

Recently, the smart grid has become a hot issue and interest in related power sources have increased accordingly. The implementation of a smart grid can enable many generation resources to be linked to the power system, including small-scale reactors for the purpose of co-generation. Research on small-scale reactors is being carried out all over the world. Similarly, Korea is also conducting research on multi-purpose regional energy systems using nuclear energy. This paper proposes a real-time data acquisition and analysis system for small-scale reactors, and is known as the REX-10 (Regional Energy rX 10 MVA). This analysis requires real-time simulations for the power system since it needs data communication with a remote REX-10. A RTDS (Real Time Digital Simulator) has been used for the simulation, and a SCADA/HMI system interfaced with the RTDS is proposed for the purpose of monitoring and control of the regional energy system.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2004년도 하계학술대회 논문집 D
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• pp.2275-2277
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• 2004

Korea Next Generation Reactor(KNGR) is in the midst of being developed and will exceed Korea Standard Nuclear Power Plant(KSNP) economically. Domestic Instrumentation and Control(I&C) systems shall be applied to KNGR and the development of Control Element Drive Mechanism Control System(CEDMCS) considered as an essential part in nuclear I&C system will be dealt with in this paper. The newly developed CEDMCS has the control cabinet using the nuclear Distributed Control System(DCS) made in Korea and the power cabinet produced by our research institute and interfaced with the DCS control cabinet.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1995년도 추계학술발표회논문집(1)
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• pp.153-158
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• 1995

All of the nuclear power plants in Korea we operating with analog instrumentation and control (I&C) equipment which are increasingly faced with frequent troubles, obsolescence and high maintenance expenses. Electrical and computer technology has improved rapidly in recent years and has been applied to other industries. So it is strongly recommended we adopt modern digital and computer technology to improve plant safety and availability. The advanced I&C system, namely, Integrated Intelligent Instrumentation and Control System (I$^3$CS) will be developed for beyond the next generation nuclear power plant. I$^3$CS consists of three major parts, the advanced compact workstation, distributed digital control and protection system including Automatic Start-up/shutdown Intelligent Control System (ASICS) and the computer-based alarm processing and operator support system, namely, Diagnosis, Response, and operator Aid Management System (DREAMS).

• 방사성폐기물학회지
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• 제21권3호
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• pp.315-327
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• 2023

In South Korea, the exporters of items related to nuclear power generation are diversified. Consequently, there is a risk of illegitimate export by companies failing to recognize the export control system because the awareness about this system for the strategic items among the subcontractors of nuclear power facilities is limited. To prevent illegitimate export of the strategic items, it is necessary to conduct outreach activities regarding the export control system for the related companies. Additionally, the exporters and export license examiners should consider whether an export target is on the Denial List, who may divert the strategic items to weapons of mass destruction. Therefore, the Korea Institute of Nuclear Nonproliferation and Control developed two systems for controlling illegitimate export of the Trigger List items. The first system, Nuclear Industry Information Collection and Analysis System, can gather information about the key nuclear industries in Korea and analyze the dealing of strategic items. The second system, Denied Persons Information Gathering System, can regularly gather information about the denied persons and provide the updated data to the exporters and regulatory examiners. These two systems can be used for outreach activities and export license examination to prevent illegitimate export of the strategic items.

• 한국태양에너지학회 논문집
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• 제34권2호
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• pp.73-81
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• 2014

Ocean thermal energy conversion(OTEC) is a power generation method that utilizes temperature difference between the warm surface seawater and cold deep sea water of ocean. As potential sources of clean-energy supply, Ocean thermal energy conversion(OTEC) power plants' viability has been investigated. Therefore, this paper evaluated the thermodynamic performance of solar-OTEC convergence system for the production with electric power and desalinated water. The comparison analysis of solar-OTEC convergence system performance was carried out as the fluid temperature, saturated temperature difference and pressure of flash evaporator under equivalent conditions. As a results, maximum system efficiency, electric power and fresh water output show at 40, 10, 2.5 kPa of the flash evaporator pressure, respectively. And their respective enhancement ratios were approximately 6.1, 18, 8.6 times higher than that of the base open OTEC system. Also, performance of solar-OTEC system is the highest in the flash evaporator pressure of 10 kPa.

• 대한전기학회:학술대회논문집
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• 대한전기학회 1987년도 정기총회 및 창립40주년기념 학술대회 학회본부
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• pp.150-153
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• 1987

This paper describes the fundamentals, system configuration, existing situation and future prospect of the cogeneration system and valuation of its economic effects. Especially, increasing this system should be evaluated for national energy management deeply, because KEPCO has generation units eneugh which can be met demend currently and in the near future and nuclear power generation has been more than 50% of total generation.

• Nuclear Engineering and Technology
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• 제49권5호
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• pp.905-913
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• 2017

Advanced reactor designs often feature longer operating cycles between refueling and new concepts of operation beyond traditional baseload electricity production. Owing to this increased complexity, traditional proportional-integral control may not be sufficient across all potential operating regimes. The prototypical advanced reactor (PAR) design features two independent reactor modules, each connected to a single dedicated steam generator that feeds a common balance of plant for electricity generation and process heat applications. In the current research, the PAR is expected to operate in a load-following manner to produce electricity to meet grid demand over a 24-hour period. Over the operational lifetime of the PAR system, primary and intermediate sodium pumps are expected to degrade in performance. The independent operation of the two reactor modules in the PAR may allow the system to continue operating under degraded pump performance by shifting the power production between reactor modules in order to meet overall load demands. This paper proposes a Takagi-Sugeno (T-S) fuzzy logic-based power distribution system. Two T-S fuzzy power distribution controllers have been designed and tested. Simulation shows that the devised T-S fuzzy controllers provide improved performance over traditional controls during daily load-following operation under different levels of pump degradation.