• Nuclear Engineering and Technology
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• v.27 no.5
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• pp.730-742
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• 1995

The steam generator feedwater and level control system is designed by two steps of the feedwater control design and the feedback loop controller design. The feedwater sen system is designed by the optimal LQR/LQG approach and then is modified by the LTR method to recover the robustness. The plant characteristics are subject to change with the power variation and these dynamic properties are considered in the design of the feedback controller. All the designs are made in the continuous domain and are digitalized by applying the proper sampling period. The system is simulated for the two cases of power increase and decrease. From the results of simulation, it is found that the controller constants would rather be invariable during the power increase, while for the case of power decrease they should be changed with the power variation to keep the system stability.

• Proceedings of the Korea Society of Information Technology Applications Conference
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• 2005.11a
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• pp.107-112
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• 2005

This paper deals with a fault detection system design for uncertain nonlinear systems modelled as T-S fuzzy systems with the integral quadratic constraints. In order to generate a residual signal, we used a left coprime factorization of the T-S fuzzy system. From the filtered signal of the residual generator, the fault occurence can be detected effectively. A simulation study with nuclear steam generator level control system shows that the suggested method can be applied to detect the fault in actual applications.

• Journal of the Korean Institute of Intelligent Systems
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• v.13 no.3
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• pp.322-327
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• 2003

The water level of a steam generator of pressurized light water nuclear Power generator is known as a subject whose control is difficult because of a shrinking and swelling effect that is been mutually contradictory in a variation of feed water. In this paper, a neural network model selects first coordinative controller by a inappropriate gain of two PI controllers and the selected controller＇s gain is tuned by a fuzzy self-tuner. Model inputs consist of the water level, the feed water, and the stream flow. One controller of both coupling controllers whose gain is handled firstly is decided based upon above data. The proposed method can analyze patterns of signals using the characteristic of neural networks and select one controller that needs to be tuned through the observed result in this paper. If one controller between both the water level controller and the feed water controller is selected by the neural network model then a gain of the PI controller is suitably tuned by the fuzzy self-tuner. Rules of the fuzzy self-tuner drew from the pattern of input and output data. In the summary, the goal of this Paper is to select the suitable controller and tune the control gain of the selected controller suitably through such two processes.

• Nuclear Engineering and Technology
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• v.27 no.3
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• pp.317-326
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• 1995

The oater level control system of the steam generator in a pressurized water reactor and its control Problems are analysed. In this work a stable control strategy Particularly during low Power operation based on the fuzzy control method is studied. The control strategy employs substitutional information using the bypass valve opening instead of incorrectly measured signal at the low How rate as the fuzzy variable of the flow rate during low power operation, and includes the flexible scale adjusting method for fast response at a large transient. A self-tuning algorithm based on the control performance and the descent method is also suggested for tuning the membership function scale. It gives a practical way to tune the controller under real operation. Simulation was carried out on the Compact Nuclear Simulator set up at Korea Atomic Energy Research Institute and its result showed the good performance of the controller and effectiveness of its tuning.

• 제어로봇시스템학회:학술대회논문집
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• 1997.10a
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• pp.17-19
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• 1997

원자력 발전소용 증기발생기의 수위제어에 기존의 경우 주로 PI제어기를 이용하는데 반해 본 논문에서는 기타의 주급수유량에 대한 주증기 유량의 변화를 2-자유도 PID제어기를 이용해 제어하는 문제를 연구하였다. 2-자유도 PID제어기의 파라메터 .alpha..betha..gamma.를 외란에 대해 가인하도록 하고 설정치변화에 대해서는 기존의 PID 파라메터가 부담하도록 함으로서 외란 및 설정치 모두에 대해 고찰한 결과 기존의 PI제어기에 비해 성능이 우수함을 나타내었다.

• Proceedings of the KIEE Conference
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• 2000.11a
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• pp.259-261
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• 2000

MPC 제어기가 고정된 출력준위에서 선형 증기발생기 모델을 위해 설계되었다. 고정된 출력준위에서 설계된 제어기는 단지 입력가중치만을 변경하므로써 어떤 다른 출력준위에서 좋은 성능을 보여주었다. 또한 증기발생기는 비선형 특성을 갖고 있기 때문에 제안된 제어 알고리듬이 실질적인 성능 및 안전성을 검증하기 위하여 증기발생기의 비선형 모델에 적용되었으며, 좋은 성능을 보여주었다.

• 제어로봇시스템학회:학술대회논문집
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• 2000.10a
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• pp.550-550
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• 2000

This paper proposed a web-based open architecture monitoring system using the Java language. The proposed system can be implemented in any platform and the status of the process can be monitored in a remote station. The proposed scheme have been applied to a steam generator level controller for a nuclear power plant. The result shows the feasibility of the proposed system.

• Proceedings of the KIEE Conference
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• 1997.07b
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• pp.547-549
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• 1997

원자력 발전소용 증기발생기의 수위제어에 기존의 경우 주로 PI 제어기를 이용하는데 반해 본 논문에서는 주급 수유량에 대한 주증기 유량의 변화를 신경망을 이용해 학습함으로서 PI제어기의 각 파라메터를 뉴닝하는 문제를 연구하였다. 적용하여 고찰한 결과 기존의 PI 제어기에 비해 수위변화에 대한 추종성능이 우수함을 나타내었다.

• Journal of the Ergonomics Society of Korea
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• v.32 no.1
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• pp.1-7
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• 2013

Objective: This study proposes the application of Ecological Interface Design(EID) method that is effective for situation awareness in digitalized environment. Background: While cognitive interface design method such as Information Rich Display(IRD) is simply focused on existing information for user, EID method helps users' resource to be solved to higher ion task such as diagnostic and problem solving. Method: Using EID method based on Work Domain Analysis (WDA), it was analyzed and designed for Steam Generator(SG) Water Level control process in a digitalized Main Control Room of Nuclear Power Plant. Proposed EID example is evaluated through interviews by expert & operator. Results: The result of expert & operator showed that EID display might give an aid for operator's decision. Conclusion: The results can reduce critical accidental damage that occurred due to cognitive load and so critical human error. Application: This study may be impact on situation awareness study for digitalized interface design.

• Journal of the Korean Society of Safety
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• v.30 no.5
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• pp.131-137
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• 2015

For the evaluation of safety margin of a nuclear power plant using a conservative methodology, the influence of applied assumptions such as initial conditions and boundary conditions needs to be assessed deliberately. Usually, a combination of the most conservative initial conditions is determined, and the safety margin for the transient is evaluated through the analysis for this conservative conditions. In existing conservative methodologies, a most-conservative condition is searched through the analyses for the maximum, minimum, and nominal values of the major parameters. In the present study, we investigates a new approach which can be applied to choose a most-conservative initial condition effectively when a best-estimate computer code and a conservative evaluation methodology are utilized for the evaluation of safety margin of transients. By constituting the band of various initial conditions using the random sampling of input parameters, the sensitivity study for various parameters are performed systematically. A method of sampling the value of control or operation parameters for a certain range is adopted by use of MOSAIQUE program, which enables to minimize the efforts for achieving the steady-state for various different conditions. A representative control parameter is identified, which governs the reactor coolant flow rate, pressurizer pressure, pressurizer level, and steam generator level, respectively. It is shown that an appropriate distribution of input parameter is obtained by adjusting the range and distribution of the control parameter.