• 한국정밀공학회지
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• 제16권12호
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• pp.78-86
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• 1999

The improvement of the water level control is important since it will prevent the steam generator trip so that improve the reliability and credibility of operation system. In this paper, the closed loop system identification is performed which can be used for the system monitoring and prediction of the system response. The model also can be used for the prediction control. Irving model is used as a steam generator model. The plant is an open loop unstable and non-minimum phase system. Fuzzy controller stabilize the system and the stable controller stabilize the system and the stable closed loop system is identified using neural networks. The obtained neural network model is validated using the untrained input and output. The results of computer simulation show the obtained Neural Network model represents the closed loop system well.

• 대한전자공학회:학술대회논문집
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• 대한전자공학회 2003년도 하계종합학술대회 논문집 Ⅲ
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• pp.1295-1298
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• 2003

The steam generator level in a PWR is very difficult to control particularly at low power. And the constant control gain and time value are not adaptive in steam generator level controller. In normal operation constant control gain and time value have no problem. But there is problem at low power. So variable control gains based on the temperature are required. The best control gain is decided by the experienced knowledge. A fuzzy gain tuner is used for the gain tuning. In the design of fuzzy gain-tuner processing, the experienced knowledge is employed for making fuzzy rules.

• 조명전기설비학회논문지
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• 제16권3호
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• pp.101-109
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• 2002

원자력발전소 제어계통중 운전 정지에 많은 영향을 주고 제어하기 가장 까다로운 중기발생기 수위 제어는 특히 기동시 및 저 출력시에 자동제어는 물론 수동제어도 매우 어려운 상태이다. 중기발생시 수위특성을 분석하여 안정성이 보장된 증기발생기 수위 제어 계통의 제어방법을 개선하여 제어 성능과 신뢰도를 향상시킬 수 있는 알고리즘을 개발하고 디지털 제어 시스템으로 구현하여 실제 발전소에 설치 적용하였다.

• 대한전기학회:학술대회논문집
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• 대한전기학회 1995년도 추계학술대회 논문집 학회본부
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• pp.172-174
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• 1995

About a half of Electric power is generated by nuclear power plants in korea. So, the stable operation of nuclear power plant is very important for suppling the essential national electric power. A S/G(Steam Generator) level control is the most difficult system in PWR(Pressurized Water Reactor) nuclear power plant. Because of the non-linear and the non-nominal response of S/G level control, it Is very difficult to control the level by automatic mode or manual mode. The goal of this study is to establish and verify a advanced control algorithm by analyzing, modelling, stability calculation, controller parameter calculation, simulation for S/G level control system.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2005년도 학술대회 논문집 정보 및 제어부문
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• pp.328-330
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• 2005

Most of the water level controllers of the actual plant are PID controllers. But they have limitations in appling for tracking the set point and getting rid of disturbances, so there are some defects to apply in the actual ground even though many research works represented the resolution to solve it. In this paper, we design a fuzzy logic system (FLS) for controlling the steam generator water level in nuclear power plants. Some computer simulations reveal similar performance with the conventional PID controller.

• Nuclear Engineering and Technology
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• 제27권1호
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• pp.8-17
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• 1995

최근 디지탈 기술을 응용하여 원자력 발전소 제어 시스템의 성능을 향상시키려는 많은 노력이 있어 왔고, 차세대 원자로에 구현할 것을 목표로 디지탈 제어 시스템 개발에 관한 장기적인 계획이 수립되어 있다. 디지탈 제어 시스템을 구축하고자 할 때 적정한 샘플링 주기를 정하는 것은 중요한 과정이다. 제어기의 안정성과 성능은 샘플링 주기에 밀접한 관련이 있다 현재 디지탈 제어기의 샘플링 주기를 체계적으로 정하는 전형적인 방법은 없다. 일반적으로 디지탈 제어기의 안정성을 고려해서 연속시간역 제어의 대역폭의 20∼30배의 역수 정도의 샘플링 주기를 흔히 쓴다. 이 논문에서는 안정성 뿐 아니라 시간역에서의 좋은 성능을 보장받을 수 있는 적정한 샘플링 주기를 얻을 수 있는 방법을 제시하였다. 이 방법으로 Irving의 모델을 이용하여 디지탈제어기의 적정 샘플링 주기를 예측하고, 고리 2호기의 마이크로 시뮬레이터와 WDPF 디지탈 제어기를 이용한 증기 발생기 수위제어 모사시스템에서 검증해 본 결과, 고리 2호기 원자력발전소 중기 발생기 수위제어를 위한 디지탈 제어기의 원자로 전 출력영역에 대한 적정 샘플링 주기 가 1초가 되는 것을 알게 되었다.

• Nuclear Engineering and Technology
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• 제56권1호
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• pp.257-264
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• 2024

The sodium cooled fast reactor (SFR) is one of the Gen-IV reactors with the most operating experience accumulated. Although the technology level is the most mature among the Gen-IV reactors, there is still a safety problem that has not been solved, which is the sodium-water reaction. Since sodium and water are separated only by a heat transfer tube with a thickness of only a few mm, there is inherently a risk of a sodium-water reaction (SWR) accident in the SFR. In this study, it is attempted to quantitatively evaluate the resistance of SWR accidents by replacing the shell and tube steam generator with printed circuit steam generator (PCSG) as a method to mitigate the SWR accident. To do this, a CATS-S (Compact Accident Tolerance Steam Generator-SWR) facility was designed and built. And for the quantitative evaluation of accident resistance, a methodology for measuring the impingement wastage rate was established. As a result of this research, the impingement wastage rate caused by SWR generated in a PCSG was measured first time. It was confirmed that the impingement wastage phenomenon was suppressed in the PCSG, and the accident resistance was higher than that of the SWR through comparison with the experimental results performed in the existing shell and tube steam generator. In conclusion, a PCSG is more resistant to impingement wastage as a result of the SWR accident than existing shell and tube steam generators, and it is estimated that a PCSG can mitigate SWR accidents, an inherent problem of SFR.

• Nuclear Engineering and Technology
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• 제26권1호
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• pp.32-40
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• 1994

중기발생기의 수위조절과 관련하여 최적제어이론을 이용한 디지탈 제어시스템을 설계하였다. 우선 급수변을 일차 지연함수로 취급하여 전체 시스템에 포함시킴으로써 보다 실제에 가까운 시스템이 되게 하였다. LQ 방법을 이용하여 급수변의 작동 및 요구신호량과 급수출력과의 차이를 최소화시킬 수 있는 최적 이득상수를 결정하였으며, 아울러 저출력에서의 급수유량 측정이 불확실함을 고려하여 급수신호에 대한 칼만 관측기를 설계하였다. 그리고 전출력 구간에서 일정한 안정여유도를 유지시킬 수 있는 가변상수 디지탈 제어기를 설계하였다. 이러한 제어시스템은 보다 현실적인 상황을 반영하고 있으며 저출력에서 급수와 반대현상을 보이는 중기발생기의 동특성에도 불구하고 만족할만한 제어특성을 보이고 있다.

• 대한전기학회:학술대회논문집
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• 대한전기학회 1993년도 하계학술대회 논문집 A
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• pp.261-264
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• 1993

This paper proposes an adaptive generalized predictive control with feedforward algorithm for steam generator level control in nuclear power plant. The proposed algorithm is shown that the parameters of N-step ahead predictors can be obtained using the parameters of one-step ahead predictor which is derived from plant model with feedforward. Using this property the proposed scheme is an adaptive algorithm which consists of GPC method and the recursive least squares algorithm for identifying the parameters of one-step ahead predictor. Also, computer simulations are performed to evaluate the performance of proposed algorithm using a mathematical model of PWR steam generator Simulation results show good performances for load variation. And the proposed algorithm shows better responses than PI controller does.

• 제어로봇시스템학회논문지
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• 제2권4호
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• pp.306-311
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• 1996

This paper discusses the maintenance of the water level of steam generators at its programmed value. The process, the water level of a steam generator, has the nonminimum phase property. So, it causes a reverse dynamics called a swell and shrink phenomenon. This phenomenon is severe in a low power condition below 15 %, in turn makes the start-up of the power plant too difficult. The control algorithm used here incorporates a pole-assignment scheme into the minimum variance strategy and we use a parallel adaptation algorithm for the parameter estimation, which is robust to noises. As a result, the total control system can keep the water level constant during full power by locating closed-loop poles appropriately, although the process has the characteristics of high complexity and nonlinearity. Also, the extra perturbation signals are added to the input signal such that the control system guarantee persistently exciting. In order to confirm the control performance of a proposed pole-assignment self-tuning controller we perform a computer simulation in full power range.