• 한국대기환경학회지
• /
• 제31권5호
• /
• pp.461-471
• /
• 2015

Base on emission factors derived from National Institute of Environmental Research, Particulate matter from combined cycle power plants (CCPPs) has been estimated to be a important source of $PM_{10}$. Generally there is no serious emission of particulate matter in CCPPs. because the fuel of them is natural gas. But emission gas after long shut down season has very high dust content. Therefore $PM_{10}$ emission rate is dependent on its operation mode. In this study, particulate dispersion study for new city near CCPPs complex has performed using CALPUFF model for three case. $PM_{10}$ concentration has big difference between normal operation and 2 case start-up condition after long shutdown. In normal operating conditions, daily $0.32{\sim}0.50{\mu}g/m^3$ influence on of the surrounding area. But when 1~2 aerobic high concentration discharged conditions, average concentration is higher about $9.2{\sim}34.1{\mu}g/m^3$ than normal operating conditions.

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

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

• 한국경영정보학회:학술대회논문집
• /
• 한국경영정보학회 2007년도 추계학술대회
• /
• pp.309-315
• /
• 2007

SK텔레콤은 급변하는 이동통신시장 환경의 변화에 적절히 대응하기 위하여 지난 10여 년간 사용해 온 메인프레임 기반의 COIS 시스템을 중단하고 Unix 기반의 NGM 시스템으로 다운사이징하기로 결정하였다. 2002 년 9 월 SK 텔레콤은 차세대 IT 인프라 혁신 전략 프로젝트를 완료하고 이에 근거하여 2003 년 말 1 단계 프로젝트를 추진하게 된다. 그러나 개발 툴의 문제점, Governance 의 확보 실패 등 문제점이 계속 누적되어 2005년에 접어들어서는 총체적 난국 상황에 봉착하게 되었다. 2005 년 2 월 자체 점검 결과 개발 진척도는 50%에 불과한 상황이었다. 결국 2005 년 3 월, NGM 추진본부는 프로젝트의 추진 중단을 선언하기에 이르렀다. NGM 프로젝트는 처음부터 재 검토하여 Re-planning 을 실시한 후 구축을 재개하기로 결정하였다. 2005 년 5 월 NGM 프로젝트의 Re-plan 이 수립되었다. 우선 Turn-key 방식의 문제점을 해소하기 위하여 SK 텔레콤이 구축의 총책임을 떠맡고, SK C&C 가 시스템 이행에 대한 책임을 지는 Governance 체제를 확립하였다. 또한 2 단계 프로젝트에서는 NGM 프로젝트를 기술적으로 원점부터 재 검토하여 이전과는 근본적으로 다른 In-House 구축 접근방식을 채택하기로 하였다. 2 단계 프로젝트에서 관심을 집중한 기술적 의사결정 영역은 크게 (1) 미들웨어 및 개발프레임워크의 적용, (2) DB 아키텍처의 결정 및 슬림화, (3) 시스템 성능 개선 등의 세 분야로 집약할 수 있다. 이 논문에서는 이들 각각의 분야를 구체적으로 검토하였다. 결국 2006 년 10 월 9 일 메인프레임 기반의 COIS 는 Shut-down 되어 가동을 멈추었고, Unix 기반의 NGM 시스템이 가동을 개시함으로써 차세대 마케팅을 본격 추진하기 위한 다운사이징 프로젝트가 성공적으로 완수되었다.

• 한국원자력학회:학술대회논문집
• /
• 한국원자력학회 1997년도 춘계학술발표회논문집(1)
• /
• pp.587-591
• /
• 1997

The DGs (Diesel Generators) in NPP (Nuclear Power Plant) has been used for the emergency electric power source to shut down the nuclear reactor safely in case of station blackout. The RCM (Reliability Centered Maintenance) has been applied to DGs for increasing the safety of NPP. The structured defects of DG were not remedied by the improvement of maintenance method. As the first stage of RCM, to find the structured defects, its failure modes were searched and analyzed through the ten year maintenance information. The structured defects such as the air compressor, the lubricating oil pressure, and the insufficient load were the root causes of main failures. The air reservoir reinstallation, the lubricating oil tube modification, the load bank installation, and the qualitative instrumentation were the solutions for the hardware oriented RCM of DGs. There remains the software oriented RCM such as the rejection of useless maintenance, the preventive maintenance, the database of maintenance information, and the predictive maintenance.

• 대한전기학회:학술대회논문집
• /
• 대한전기학회 2011년도 제42회 하계학술대회
• /
• pp.1405-1405
• /
• 2011

Sudden earthquake is changing national energy stratagem for future energy resource. In case Germany, current nuke power station will be shut down with several decades. Newly constructed build in Japan must have photovoltaic system as a obligations.. As a long-term sustainable energy one, PV should give confidence to customers up to more than 20 years. Today, IEC 61215 and IEC 61646 standards are representative one for ensuring performance and safety of PV module. But it is still needed to develop more realistic test method. For example, if we think about extreme condition like desert and North Pole, the temperature condition describe in test standards can have little effect on life time expectation of PV module. Installation speed of PV system is very high, but establishing test standards are very complex and not easy. So in this paper, I tried to open the long-term test method for PV module to ensure 25 year's old life time. It is just starting point of PV related long-term test methods. The specific and technical explanation will be shown in the following paper in detail.

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

• 한국정밀공학회지
• /
• 제14권3호
• /
• pp.156-165
• /
• 1997

In the practical control systems, the dynamic range of actuatiors is limited(or saturated) when actuators are driven by sufficiently large signals. This gives rise to a nonlinearity as a result of actuator saturation. For example, the upper limit is imposed on productive capability by available factory space and capital equipment. Other examples of those kinds of actuator saturations are a maximum torque of the actua- ting motors and a throttle position in an aircraft speed control A saturating actuator may lead not only to a large overshoot during start-up and shut-down, but also to deterioration of the performance due to the uncertainties. That is, the speed of response is decreased and, possibly, the system output may not follow the lalrge reference inputs. The large-overshoot may be accompanied by rest wind-up(or called by integra- tor wind-up) which comes from controllers with integral action in saturation operation regions. Eventually, as the overshoot increases, the system has a limit cycle or becomes oscillatorily unstable. Due to these cir- cumstances, many studies are focused on the stability and robustness of the nonlinear systems with satu- rating actuator in the time-domain as well as in the frequency-domain.

• 한국압력기기공학회 논문집
• /
• 제12권1호
• /
• pp.134-140
• /
• 2016

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.

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