In korea, 500MW standard coal fired power plants were designed and operated for the initial base load, so facility stability was prioritized from facility problem to treatment, but now we needed to research for minimizing greehouse gas emissions at the operation of coal fired power plants. research on various facilities and technologies was actively conducted to reduce environment pollutants was drastically reduced, but research and attempts on coping measures in the event of a reduction facility problem were in sufficient. this study considered investigated ways to minimized pollutants by quickly responding to logic development and application of the load runback concept in case of serious problems with environmental pollutant reduction facilities such as NOx reduction selective catalytic reduction facilities, SOx reduction wet flue gas desulpherisation facilities, and TSP(Total Suspended Particles) collection low temperature electric precipitator.

As the spread of new and renewable power generation facilities, the fixed investment cost CAPEX(Capital Expenditure) of solar power generation facilities decreases due to continuous technological development, and the impact of O&M costs that determine investment success has increased. For this reason, the importance of technologies such as accuracy of O&M cost calculation through ICT, failure prediction, and predictive maintenance have emerged. In the above paper, based on the cost-breakdown structure design and failure rate model design of the solar power generation facility using engineering estimation method, the maintenance cost of the solar power generation facility, which is a renewable power generation facility, is predicted and the maintenance cost used was compared and confirmed. In addition, the cost-breakdown structure and failure rate model of solar power generation facilities were designed and developed by incorporating them into a new program of economic evaluation of new and renewable power generation facilities.

The spatial variation characteristics of seismic motions at the nuclear power plant's site and structures were analyzed using earthquake records obtained at the Fukushima nuclear power plant during the Great East Japan Earthquake. The ground responses amplified as they approached the soil surface from the lower rock surface, and the amplification occurred intensively at about 50 m near the ground. Due to the soil layer's nonlinear characteristics caused by the strong seismic motion, the ground's natural frequency derived from the response spectrum ratio appeared to be smaller than that calculated from the shear wave velocity profile. The spatial variation of the peak ground acceleration at the ground surface of the power plant site showed a significant difference of about 0.6 g at the maximum. As a result of comparing the response spectrums at the basement of the structure with the design response spectrum, there was a large variability by each power plant unit. The difference was more significant in the Fukushima Daiichi site record, which showed larger peak ground acceleration at the surface. The earthquake motions input to the basement of the structure amplified according to the structure's height. The natural frequency obtained from the recorded results was lower than that indicated in the previous research. Also, the floor response spectrum change according to the location at the same height was investigated. The vertical response on the foundation surface showed a significant difference in spectral acceleration depending on the location. The amplified response in the structure showed a different variability depending on the type of structure and the target frequency.

A heat pump system using wasted heat from thermal effluent to supply the heating energy can reduce energy consumption and emissions of greenhouse gases by greenhouse facilities nearby. The Jeju National University consortium constructed a heat pump system using the thermal effluent from the Jeju thermal power plant of KOMIPO to provide with cool or hot water to greenhouse facilities located 2.5km from the power station. In this paper, the system configuration of the heat pump system was summarized, and the results of operations for demonstration of a heating performance carried out during the winter season in 2018 were investigated. Therefore, if the heating control by supplying thermal effluent to the facility greenhouse, it can contribute to reducing the energy cost and improving quality.

In this study, by using a system analysis program(Fluid Flow), the correlation between the location where cladding damage occurs frequently inside the power plant seawater pipe and flow characteristics is analyzed, and the root cause and improvement plan are reviewed. As a result, it was confirmed that a high flow velocity occurred in the backwash piping(7.64m/s) and the front and rear ends of the flow control valve(5.93m/s). In addition, it was confirmed that cavitation occurs when the seawater level decreases below the saturated water vapor pressure at the rear end of the orifice. These areas are locations where the internal cladding damage occurs frequently in power plants, and the main cause of damage is considered to be excessive flow velocity and cavitation in the pipe. In order to solve this problem, improvement method such as installation of backwash pipe orifices, change of pipe shape at the front and rear end of flow control valve, and change of orifice type were derived.

원자력 발전소에 지진격리장치를 설치하여 내진성능을 향상시킬 수 있다. 그러나 지진격리장치의 적용으로 지반과 구조물 사이에서 큰 상대 변위가 발생하게 된다. 따라서 지진격리된 구조물과 일반 구조물을 연결하는 연결배관시스템의 경우 지진리스크가 증가할 수 있다. 따라서 이러한 배관시스템의 지진취약도를 분석할 필요가 있다. 본 연구에서는 지진취약도 분석 을 위해 지진격리된 APR1400 원자력발전소와 주증기관을 대상으로 지진취약도를 분석하였다. 주증기관은 지진격리된 nuclear island의 보조 건물과 터빈 건물을 연결하는 인터페이스 배관이다. 지진취약도 분석을 위한 파괴모드는 누출관통균열로 정의하였다. 누출은 실험결과와 수치해석을 통해 손상지수로 정량화하여 취약도 분석을 위한 파괴기준으로 사용하였다. 파괴기준의 변동에 의한 취약도 곡선의 변동성을 확인하기 위하여 손상지수의 최솟값, 최댓값, 평균값 및 중앙값을 파괴기준으로 하여 지진취약도 곡선을 작성하였다.

본 연구에서는 광화학 대기질 모델인 CMAQ을 활용해 화력발전소 배출량 제거에 따른 O3 농도의 변화 특성을 분석하였다. 하동 화력발전소를 대상으로 주변 지역의 O3 농도 변화에 대한 발전소 배출량의 영향을 조사하기 위해 하 동 화력발전소의 배출량 제거 전과 후의 CMAQ 수치 모의를 수행하였다. 수치 모의 결과 O3의 주요 전구 물질인 NOx (-18.87%)와 VOCs (-11.27%)의 농도가 감소한 반면에 O3 (25.24%)의 농도는 증가한 것으로 나타났다. 화력발전소 배출량 제거로 인한 NO와 O3 농도의 상대적인 변화를 비교해 본 결과 높은 음의 상관관계(R= -0.72)를 나타내는 것이 확인되었다. 이러한 결과는 O3의 농도 증가가 NO 농도 감소로 인한 O3의 적정 효과 완화로 설명 될 수 있음을 의미한 다. 해당 지역의 O3의 농도 증가가 NO의 농도 감소에 주로 영향을 받은 이유는 해당 지역이 VOC-limited (i.e., NOxsaturated) 지역이기 때문으로 분석되었다. 이러한 결과는 특정 지역의 O3의 농도가 단순히 배출량의 증감에 따라 비례하게 나타나지 않을 수 있다는 것을 암시한다. 따라서 화력발전소 배출량 저감 조치로 인한 대기 중 O3 농도 개선 효과를 정확히 예측 및 평가하기 위해서는 지역 별 O3의 생성 및 소멸 기작에 대한 심도 있는 이해가 필요하다.

We conducted a study on the possibility of using the power plant's thermal effluent system by using a heating system to utilize the thermal effluent from Jeju Power Headquarters of KOMIPO. In this study, growth information such as the size, leaf area, fresh weight and dry weight of subtropical persimmon fruit (A) in the facility cultivation complex were measured. In the comparison group (B), the growth information of the same crop was measured and compared in an unheated greenhouse near Harye-ri, Namwon-eup, Seogwipo. Fruit size was measured at monthly intervals, and leaf area, fresh weight, and dry weight were measured at new shoot season. Measurement results of A and B growth information, 1) Fruit diameter & length, A grew 7.3% and 9.4% than B, 2) Leaf area, A grew 4.7% than B, 3) Fresh weight, the decrease was 8.9%, but the dry weight was 3.6%, indicating that A contains more nutrients than B. Therefore, if the heating control by supplying thermal effluent to the facility greenhouse, it can contribute to reducing the energy cost and improving quality.

Analysis of the 2016 Gyeongju earthquake and the 2017 Pohang earthquake showed the characteristics of a typical high-frequency earthquake with many high-frequency components, short time strong motion duration, and large peak ground acceleration relative to the magnitude of the earthquake. Domestic nuclear power plants were designed and evaluated based on NRC's Regulatory Guide 1.60 design response spectrum, which had a great deal of energy in the low-frequency range. Therefore, nuclear power plants should carry out seismic verification and seismic performance evaluation of systems, structures, and components by reflecting the domestic characteristics of earthquakes. In this study, high-frequency amplification factors that can be used for seismic verification and seismic performance evaluation of nuclear power plant systems, structures, and equipment were analyzed. In order to analyze the high-frequency amplification factor, five sets of seismic time history were generated, which were matched with the uniform hazard response spectrum to reflect the characteristics of domestic earthquake motion. The nuclear power plant was subjected to seismic analysis for the construction of the Korean standard nuclear power plant, OPR1000, which is a reactor building, an auxiliary building assembly, a component cooling water heat exchanger building, and an essential service water building. Based on the results of the seismic analysis, a high-frequency amplification factor was derived upon the calculation of the floor response spectrum of the important locations of nuclear power plants. The high-frequency amplification factor can be effectively used for the seismic verification and seismic performance evaluation of electric equipment which are sensitive to high-frequency earthquakes.

본 연구는 화력발전소 배출로 인한 지표면 오염물질 농도의 시·공간적 영향을 실측 자료를 바탕으로 정량적으로 분석하려는 목적으로 수행되었다. 배출과 농도 관계의 정량적 분석을 위해 우선 기상 조건과 주변 배출원의 영향을 고려하였다. 이를 위해 자료의 선택과 관측지점 선정 과정을 제안하였고, 선정된 지표면 시·공간 자료에 K-Z 필터와 경험직교함수(EOF) 분석 기법을 적용하였다. 사용된 자료는 2014-2017년 4년의 기간 동안 당진과 태안 화력발전소 굴뚝 자동측정기기의 농도값을 이용하여 산출한 한 시간 평균 배출량 자료와 지표면 대기오염농도 측정망 자료이다. 기상 자료로는 최근 배포 중인 ERA5 재분석자료와 기상청 종관기상관측소 한 시간 평균 자료가 사용되었다. 발전소만의 영향이 최대한 보이도록 기상 효과와 지리적인 요인을 고려하여 선택한 시간대의 선정된 관측소 자료만을 이용하여 분석한 결과, 지표면 대기오염물질의 EOF 첫 번째 모드는 SO2, NO2, PM10 모두에 대해 97% 이상의 변동성을 설명하였다. 또한 지표면 농도장의 EOF 첫 번째 모드의 시계열은 화력발전소 배출과 유의미한 상관성을 보였다. 결과적으로 당진 화력발전소 SO2, NO2, TSP 시간 당 배출량이 각각 10%가 감소하면, 남서풍 계열의 바람에 의해 직접 영향을 받는 서울 수도권 지표면 평균 SO2 농도는 0.468 ppb (R=0.384), NO2는 1.050 ppb (R=0.572), PM10은 2.045 μg m−3 (R=0.343) 정도가 감소한다고 판단할 수 있다. 태안화력발전소의 경우, SO2, NO2, TSP 배출량을 각각 시간당 10% 씩 감축하면, SO2는 0.284 ppb (R=0.648), NO2는 0.842 ppb (R=0.683), PM10은 1.230 μg m−3 (R=0.575) 정도가 감소될 수 있음을 확인하였다. 태안화력발전소는 당진화력발전소에 비해 수도권지역 농도에 미치는 영향은 작았으나, 상관관계는 더 높았다.

본 연구에서는 기존 상용 SCR 촉매보다 비표면적, 경량성 및 온도 응답성이 우수한 SCR 촉매의 개발을 목적으로 바나듐과 텅스텐의 함량과 바인더의 첨가량을 달리하여 Metal foam 형태의 지지체에 코팅하여 SCR 촉매를 제조한 후, 실험실 규모의 마이크로 상압반응기상에서 공간속도별로 NOx 저감 성능을 측정하였다. 촉매의 특성은 Porosimeter, SEM(scanning electron microscope), EDX(energy dispersive x-ray spectrometer) 및 ICP(inductively coupled plasma), 실체현미경(Stereomicroscope) 기기를 이용하여 분석하였다. 연구 결과 NOx 저감 성능은 공간속도가 증가할수록 감소하였고, 바나듐과 텅스텐의 함량이 3.5 wt.% 일 때 가장 우수한 것으로 확인하였다. 또한, 바인더 첨가량이 많을수록 NOx 저감 성능이 감소하는 것으로 나타났는데, 이는 촉매 표면상의 활성점수가 바인더에 의해 점유되어 감소된 것에 따른 것으로 판단된다. 또한 표면 코팅 상태 분석을 통하여 바인더의 첨가량이 적절히 조절 되어야 함을 알 수 있었다.

In this study, a plate heat exchanger was developed for applying to a heat pump system using the heated effluent from a thermal power plant. Since seawater is used as a heat source and a heat sink in this heat pump system, Titanium was chosen as the heat plate material for its high corrosion resistance. One of the purposes of the study was to get an optimized distribution area in the heat plate in order that better thermal performances could be achieved through equal flow rates along the heat transfer area. It was revealed from the performance tests that the mean heat transfer rate and the overall heat transfer coefficient were enhanced by 2.9% and 7.7%, respectively, compared to those measured before the design optimization.

Recently, the continuing operation of nuclear power plants has become a major controversial issue in Korea. Whether to continue to operate nuclear power plants is a matter to be determined considering many factors including social and political factors as well as economic factors. But in this paper we concentrate only on the economic factors to make an optimum decision on operating nuclear power plants. Decisions should be based on forecasts of plant accident risks and large and small accident data from power plants. We outline the structure of a decision model that incorporate accident risks. We formulate to decide whether to shutdown permanently, shutdown temporarily for maintenance, or to operate one period of time and then periodically repeat the analysis and decision process with additional information about new costs and risks. The forecasting model to predict nuclear power plant accidents is incorporated for an improved decision making. First, we build a one-period decision model and extend this theory to a multi-period model. In this paper we utilize influence diagrams as well as decision trees for modeling. And bayesian statistical approach is utilized. Many of the parameter values in this model may be set fairly subjective by decision makers. Once the parameter values have been determined, the model will be able to present the optimal decision according to that value.