• 시스템엔지니어링학술지
• /
• 제16권2호
• /
• pp.1-15
• /
• 2020

Nuclear power plants in South Korea are operated to cover the baseload demand. Hence they are operated at 100% rated power and do not deploy power tracking control except for startup, shutdown, or during transients. However, as the contribution of renewable energy in the energy mix increases, load follow operation may be needed to cover the imbalance between consumption and production due to the intermittent nature of electricity produced from the conversion of wind or solar energy. Load follow operation may be quite challenging since the operators need to control the axial power distribution and core reactivity while simultaneously conducting the power maneuvering. In this paper, a systems engineering approach for multi-physics load follow simulation of APR1400 is performed. RELAP5/SCDAPSIM/MOD3.4/3DKIN multi-physics package is selected to simulate the Korean Advanced Power Reactor, APR1400, under load follow operation to reflect the impact of feedback signals on the system safety parameters. Furthermore, the systems engineering approach is adopted to identify the requirements, functions, and physical architecture to provide a set of verification and validation activities that guide this project development by linking each requirement to a validation or verification test with predefined success criteria.

• Nuclear Engineering and Technology
• /
• 제54권10호
• /
• pp.3878-3887
• /
• 2022

For the future energy-mix policy for carbon neutrality, demand for the capability of load-follow operation has emerged in nuclear power plants in order to accommodate the intermittency of renewable energy. The short-term decay heat analysis is also required to evaluate the decay heat level varied by the power level change during the load-follow operation, which is a very important parameter in terms of short-term decay heat removal during a grace time. In this study, the short-term decay heat level for 10 days after the shutdown was evaluated for both seasonal and daily load-follow cases. Additionally, the nuclide-wise contribution to the accumulated decay heat for 10 days was analyzed for further understanding of the short-term decay heat behavior. The result showed that in the seasonal case, the decay heat level was mainly determined by the power level right before the shutdown and the amount of each nuclide was varied with the power variation due to the long variation interval of 90 days. Whereas, in the daily case, the decay heat level was strongly impacted by the average power level during operation and meaningful mass variations for those nuclides were not observed due to the short variation interval of 0.5 days.

• 대한전기학회논문지
• /
• 제34권12호
• /
• pp.491-497
• /
• 1985

An applicaton of the linear optimal control theory to the problem or load follow control in pressurized water reactors (PWR) is investigated. In order to perform the steady-state and load follow operation in PWR, a nonlinear model for the reactor and steam generator is derived and linearized at 50% rated power. Simulation tests are performed for 10% demanded load. Comparing the dynamic response of the newly developed optimal load follow controller with those of the integral error feedback controller proposed by Yang, the rise time of dynamic response of the former is about 15 seconds faster than those of the latter, thus the results indicate that the fast response of the optimal load follow controller is verified. The results of this work are directly applicable to the design of the load follow control systems for commercially operated PWRs.

• Nuclear Engineering and Technology
• /
• 제18권3호
• /
• pp.209-217
• /
• 1986

보론 희석이 불충분한 주기 말에서 부하추종 운전영역을 확장시키기 위해 냉 각재 입구 온도 감소 방식을 사용하였으며, 이 방식을 모사하고 부하추종 운전시 가압경수로 노심의 핵적 특성을 해석하기 위해 3차원적 전산체제를 확립하였다. 해석은 고리 1호기 1주기말에서 12-3-6-3부하추종 운전에 대해 MINB 및 SPINR 모드로 수행되었으며, 부가적으로 이 두 방식에 대한 출력복귀능력도 RETRAN02 코드를 사용한 계통해석과 더불어 시험하였다. 계산결과 냉각재 입구 온도를 감소시킴으로써 부하 추종운전이 주기 말에서도 가능함이 입증되었으며 14$^{\circ}$F의 입구 온도 감소에 따라, SRC가 제어봉만 사용하는 방식보다 MINB 모드에서는 13%, SPINR모드에서는 14%까지 증가됨을 보여주었다.

• Nuclear Engineering and Technology
• /
• 제24권2호
• /
• pp.183-192
• /
• 1992

한국 표준 원전의 부하추종운전 능력 향상을 위하여 노심 축 방향 출력분포 제어에 기존의 regulating bank와는 별개의 heavy bank를 사용하는 노심 제어 기법인 Mode K를 제시하였다 이 경우 heavy bank는 제어할 수 있는 축방향 출력 변화의 범위가 크며, 또한 bank의 움직임과 축 방향 출력 변화가 단조적 관계를 항상 유지할 수 있으므로 운전을 용이하게 할 뿐 아니라 자동제어가 가능하도록 한다. Mode K기법을 이용한 노심 제어 자동화는 부하추종운전에 대한 운전원의 부담을 경감시킬 수 있으며, 특히 주파수 제어 운전등 미리 예측되지 않은 부하변동에 응동할 수 있는 능력을 갖게 한다. 표준 원전의 참조 발전소인 영광 3,4호기의 운전을 모의 계산함으로써 Mode K 의 설계 개념을 평가하였는데 그 결과를 통하여 한국 표준 원전의 실제적 부하추종운전을 위하여 Mode K 기법을 적절하게 사용할 수 있음을 입증하였다.

• 대한전기학회논문지
• /
• 제40권1호
• /
• pp.10-17
• /
• 1991

An improved control method in turbine control system is proposed. By automatic follow-up design, power system frequency may be maintained within prespecified range. Base or half load control is possible by distributing power plant load allotment. Otherwise, diminutive frequency-load control is dine by governor-free operation in power plant. This paper proposes governor-free operation which is automatically followed by load-limitter setter. The condition which limits governor action may be somewhat improved within boiler condition by this idea. This design has been implemented at Samchunpo thermal power plant. The improved practical results are shown.

• 원자력산업
• /
• 제6권5호통권39호
• /
• pp.16-22
• /
• 1986

• 한국원자력학회:학술대회논문집
• /
• 한국원자력학회 1996년도 춘계학술발표회논문집(1)
• /
• pp.231-236
• /
• 1996

The xenon dynamics module in the nuclear design code MASTER was verified through a simulation calculation. The simulation result shows that the xenon dynamics module in MASTER can trace and predict xenon behavior with accuracy under any core transient state and therefore can simulate load follow operations.

• Nuclear Engineering and Technology
• /
• 제20권1호
• /
• pp.1-8
• /
• 1988

상업용 발전소의 가동시, 출력 변화에 의해 1차 계통 보론 농도의 변화가 요구되었을 때 CVCS보충 시스템에서의 보충 유량이 연속 방정식과 질량 평형 방정식을 이용하여 측정된다. 이를 위하여, 1차 계통, 가압기, 그리고 volume control tank가 각각 질량과 보론 농도를 가진 control volume으로 그리고 1차측과 가압기, CVCS를 연결하는 파이프들이 시간 지연 요소로 모델화 되었다. 14-2-6-2 (출력변화 100-50-100) 부하 추종운전의 경우(7호기 EOL에서)를 이 모델을 이용하여 계산하였다.

• 한국원자력학회:학술대회논문집
• /
• 한국원자력학회 1999년도 추계학술발표회요약집
• /
• pp.92.1-92
• /
• 1999