• 제목/요약/키워드: Energy margin

검색결과 282건 처리시간 0.026초

수요와 공급의 불확실성을 고려한 시간대별 순동예비력 산정 방안 (Dynamic Reserve Estimating Method with Consideration of Uncertainties in Supply and Demand)

  • 권경빈;박현곤;류재근;김유창;박종근
    • 전기학회논문지
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    • 제62권11호
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    • pp.1495-1504
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    • 2013
  • Renewable energy integration and increased system complexities make system operator maintain supply and demand balance harder than before. To keep the grid frequency in a stable range, an appropriate spinning reserve margin should be procured with consideration of ever-changing system situation, such as demand, wind power output and generator failure. This paper propose a novel concept of dynamic reserve, which arrange different spinning reserve margin depending on time. To investigate the effectiveness of the proposed dynamic reserve, we developed a new short-term reliability criterion that estimates the probability of a spinning reserve shortage events, thus indicating grid frequency stability. Uncertainties of demand forecast error, wind generation forecast error and generator failure have been modeled in probabilistic terms, and the proposed spinning reserve has been applied to generation scheduling. This approach has been tested on the modified IEEE 118-bus system with a wind farm. The results show that the required spinning reserve margin changes depending on the system situation of demand, wind generation and generator failure. Moreover the proposed approach could be utilized even in case of system configuration change, such as wind generation extension.

표준 핵연료집합체 또는 최적 핵연료집합체가 장전된 원자력 1호기 원자로심의 열적여유도 분석 (Thermal Margin Analysis of the Korea Nuclear Unit 1 Reactor Core Consisting of Standard or Optimized Fuel Assemblies)

  • Hyun Koon Kim;Ki In Han
    • Nuclear Engineering and Technology
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    • 제16권3호
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    • pp.155-160
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    • 1984
  • 표준 핵연료집합체나 최적 핵연료집합체로 구성된 원자력 1호기 원자로심의 열적여유도를 기존 열설계 방법과 통계적 열설계 방법을 이용하여 분석하였다. 통계적 열설계 방법은 노심내 운전변수들의 불확실도를 통계적으로 처리함으로써 기존 방법에 비하여 열적여유도를 증가시킨다. 계산을 위하여 정상상태와 과도시 열수력분석 전산코드인 COBRA-IV-i를 사용하였다. 계산결과 통계적 설계방법은 열적여유도를 크게 증가시키며, 표준 핵 연료집 합체는 물론 최적 핵 연료집 합체가 장전된 원자력 1호기의 열설계기준을 만족시키는 것으로 밝혀졌다. 그러나 기존 열설계 방법은 원자력 1호기 노심에 최적 핵연료집합체가 장전된 경우 열설계기준을 만족시키지 못하는 것으로 밝혀졌다.

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플라이휠 에너지 저장장치 자기부상 안정성 시뮬레이션 및 실험분석 (Simulation and Experimental Analysis of Magnetic Levitation Relative Stability for the Flywheel Energy Storage)

  • 박병철;정세용;한상철;이정필;한영희;박병준
    • 전기학회논문지
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    • 제59권9호
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    • pp.1605-1610
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    • 2010
  • In this paper, the relative stability of magnetic bearing system for the flywheel energy storage is evaluated using both simulation and experimental analysis. We make the simulation model for the magnetic bearing flywheel system using the rigid body shaft model. According to international standard ISO 14839-3, We experimentally analyzed the relative stability of magnetic bearing system. Additionally using both the simulation model and experimental tests, Phase margin and Gain margin is acquired through Nyquist plot.

중수로 원전에서 액체방출밸브의 개방압력에 대한 민감도평가 (The Sensitivity Analysis for LRV Opening Pressure in CANDU)

  • 김성민;고동욱;유성창;김종현
    • 에너지공학
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    • 제24권2호
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    • pp.40-44
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    • 2015
  • 중수로 일차냉각재계통 액체방출밸브의 개방압력에 대한 안전여유 및 시간지연을 반영하여 열수력코드로 경년열화가 반영된 노심에 대해 민감도를 평가하였다. 과거에는 안전해석을 수행할 때 안전여유와 시간지연을 반영하여 평가하지 않았으나, 월성1호기 안전해석 인허가 심사과정중 반영 평가하였다. 중수로 안전해석에서 압력경계는 일차냉각재계통 액체방출밸브이다. 따라서 액체방출밸브 응동이 안전해석에 직접적인 영향을 주므로 안전여유와 시간지연 부가가 안전해석 결과에 미치는 영향을 파악하고 해석에 반영하기 위해 일차냉각재계통 과압이 걸리는 사고들에 대해 평가하였다.

마이크로그리드를 기반으로 한 중소 산업용수용가의 최대수요전력 저감방안 (The Maximum Demand Power Reduction of Small Industrial Factory based on Microgrid)

  • 장홍순;김철진;박상원
    • 전기학회논문지P
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    • 제66권1호
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    • pp.7-14
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    • 2017
  • Recently, the power consumption of industrial consumer has increased rapidly, causing problems such as lack of power reserve margin in summer and winter, and therefore there is a growing need for maximum demand power management to consumers. In this paper, we studied small microgrid system consisting of battery ESS and photovoltaic power system, applied to small and medium sized factories to reduce the maximum demand power of daily industrial power load. To verify the validity of the study, we simulated a small microgrid system using Matlab/Simulink software. As a result of applying the simulation to small and medium sized plants that consume a lot of power, it is confirmed that there is a 13% reduction in demand compared to the existing maximum demand power. This result is expected to contribute to the improvement of the power reserve margin.

최적코드를 이용한 복수기진공상실 사고의 보수적 해석 (Analysis of Loss of Condenser Vacuum Accident using a Conservative Approach with a Best-Estimate Code)

  • 정해용
    • 에너지공학
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    • 제24권4호
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    • pp.175-182
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    • 2015
  • 발전소 안전성 평가 시 최적해석 코드를 사용함으로써 코드 모델의 보수성을 최소화하고, 해석 조건의 보수성을 확보하도록 다양한 범위의 초기조건을 표본 추출하여 결정하는 방법을 수립하였다. 제시된 방법론의 적용성을 확인하기 위하여 국내 경수로를 참조발전소로 선정하고 첨두 압력이 주요 안전기준이 되는 복수기 진공상실사고에 대한 안전성평가를 수행하였다. MOSAIQUE 프로그램을 이용하여 100가지 다른 초기조건을 생성하고, 자동적으로 과도해석을 수행함으로써 가장 보수적인 결과에 대한 첨두 압력을 얻을 수 있었다. 새로운 방법론에 의해 얻어진 안전여유도는 기존의 방법론과 유사한 수준을 가졌는데, 안전성 평가를 위해 소요되는 시간과 노력을 획기적으로 줄일 수 있음을 확인하였다.

Statistical model for forecasting uranium prices to estimate the nuclear fuel cycle cost

  • Kim, Sungki;Ko, Wonil;Nam, Hyoon;Kim, Chulmin;Chung, Yanghon;Bang, Sungsig
    • Nuclear Engineering and Technology
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    • 제49권5호
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    • pp.1063-1070
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    • 2017
  • This paper presents a method for forecasting future uranium prices that is used as input data to calculate the uranium cost, which is a rational key cost driver of the nuclear fuel cycle cost. In other words, the statistical autoregressive integrated moving average (ARIMA) model and existing engineering cost estimation method, the so-called escalation rate model, were subjected to a comparative analysis. When the uranium price was forecasted in 2015, the margin of error of the ARIMA model forecasting was calculated and found to be 5.4%, whereas the escalation rate model was found to have a margin of error of 7.32%. Thus, it was verified that the ARIMA model is more suitable than the escalation rate model at decreasing uncertainty in nuclear fuel cycle cost calculation.

변압기 탭이 반영된 에너지 함수를 이용한 전압안정도 해석 (Voltage Stability Analysis Based on Energy Function Considering Tap of Transformer)

  • 이기제;최병곤;권용준;문영현;오용택;이병하
    • 대한전기학회논문지:전력기술부문A
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    • 제54권7호
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    • pp.337-344
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    • 2005
  • An energy function is derived on the basis of the EMM(Equivalent Mechanical Model) to take account of the effects of tap changer, and then the VC(Voltage Collapse) criteria is proposed to predict the voltage collapse in Power systems. The VC criterion can be evaluated by using the energy margin given by the energy gap between UEP(Unstable Equilibrium Point) and SEP(Stable Equilibrium Point) of the energy function adopted, in which it is noted that the energy contour should be considered due to energy discontinuity associated with tap changing. This paper shows that the proposed VC criterion improves the accuracy of voltage stability analysis with application to a two-bus sample system.

Dynamic Behavior of Oxide and Nitride LMR Cores during Unprotected Transients

  • Na, Byung-Chan;Dohee Hahn
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1997년도 춘계학술발표회논문집(1)
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    • pp.489-494
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    • 1997
  • A comparative transient analyses were performed for oxide and nitride cores or a large (3000 MWt), pool-type, liquid-metal-cooled reactor (LMR). The study was focused on three representative accident initiators with failure to scram : the unprotected loss-of-flow (ULOF), the unprotected transient overpower (UTOP), and the unprotected fast transient overpower (UFTOP). The margins to fuel melting and sodium boiling have been evaluated for these representative transients. The results show that there is an increase in safety margin with nitride core which maintains the physical dimensions of the oxide core.

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Flow-Induced Vibration Test in the Preheater Region of n Steam Generator Tube Bundle

  • Kim, Beom-Shig;Hwang, Jong-Keun
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1996년도 춘계학술발표회논문집(4)
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    • pp.312-318
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    • 1996
  • Flow induced vibration experiments were done to determine the vibration magnitude of tubes in the economizer tube lane region of a steam generator. The objective of this experiment is to demonstrate that the tubes are not susceptible to harmful levels of vibration at 100% of full power flow and to quantify the remaining design margin at 120% and 140% of full power flow.

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