• Journal of Industrial Convergence
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• v.18 no.4
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• pp.15-21
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• 2020

Because there are no isolation valves in condensate system of nuclear power plants, circulating water pump was shutdown for the condenser repair. When circulating water pump was shutdown, power plant output decreased about 45%. These output decreasing can minimize by establishing isolation valves. In this paper, evaluated effect to flow conditions change of condensate system, structural integrity of system, condenser pressure of in case of establish isolation valves to condensate system. Results of the evaluation, the flow rate due to the installation of the isolation valve decreased 0.3% when the valve was fully opened and 4.5% when fully closed. In addition, it was found that the vacuum degree of the condenser decreased with decreasing flow rate, but the integrity of the system was maintained.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.40 no.6
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• pp.613-619
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• 2016

A pneumatic control valve performs a major role in controlling the flow of a system or the level of a key tank in many power plants, and its performance should be guaranteed during the plant's lifetime. Its operation starts by supplying air to the pneumatic actuator or by exhausting the air from the actuator. To control the valve position, the amount of air supply or exhaust is adjusted by a control loop where various accessaries are equipped. In this paper, air leakage in the air supply line, changes in the valve packing force, and false adjustments of zero and the span of the positioner are simulated and analyzed using a 2-in pneumatic valve with a position control loop including an I/P converter and positioner, where the valve position is controlled within ${\pm}2%$ of the control pressure at 67% opening position.

• 유체기계공업학회:학술대회논문집
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• 2002.12a
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• pp.493-498
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• 2002

The letdown system of pressurized water reactor (PWR) nuclear fewer plants had experienced instabilities in letdown system due to unacceptable flow characteristics of control valves. The Korean Standard Nuclear Power Plants (KSNPs) have three flow paths in parallel for letdown new control. Each flow path consists of two offices and one isolation valve. This study evaluates the effect of orifice arrangement and valve stroke time of letdown isolation valve on the system transients because sudden flow changes due to valve actuation can generate high pressure peaks in letdown line. A pressure transient analysis has been preformed to evaluate the impact of dynamic transients. This analysis uses MMS which is a simulation code developed by EPRI based on the method of characteristics. The result shows that the pressure peak is reduced in the continuous arrangement but negligible. Additionally, it shows that the stroke time of linear type flog valve greater than 15 seconds can give more stable performance.

• Proceedings of the Computational Structural Engineering Institute Conference
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• 2006.04a
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• pp.575-580
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• 2006

Air-operated valves are extensively used for process control and system isolation functions in nuclear power plant, where the safety is primary issue. The purpose of this study is to develop structural analysis code of various air-operated valves such as globe valve, gate valve, and butterfly valve. The thrust formula is derived for valve with the expected weak areas. The expected weak areas are referred from EPRI data. The structural stress analysis is carried out by analytical and commercial FEM code, ANSYS 8.0. The numerical results are compared together and verified on program procedures.

• Transactions of the Korean Society of Mechanical Engineers B
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• v.37 no.11
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• pp.1053-1060
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• 2013

The purpose of this study is to estimate the packing friction of power-operated valve in nuclear power plants. The roll of packing in valve is preventing leakage through stem. Packing friction is highly depend on gland nut tightness which means higher reliability in sealing is lower operability. For the estimation of friction, we used statistical analysis and experimental analysis. In experimental approach, we have performed packing fY test and applied it to valve field test. In statistical approach, we have used 10 years DB of safety-related valve in nuclear power plant and analyzed packing friction based on confidence interval of sample. The comparison of two results shows that statistical analysis for packing friction are more accurate than fY analysis even though both approach have error compared to measured value but we confirmed that statistical approach is proper way to estimate packing friction.

• 제어로봇시스템학회:학술대회논문집
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• 2005.06a
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• pp.1384-1386
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• 2005

This paper focuses on development of load test simulator of a steam turbine-generator in a nuclear power plant. When load is taken off from electrical power network, it is very difficult to effectively control the steam flow to turbine of the nuclear turbine-generator, because of disturbances, such as electrical load and network unbalance on electrical network. Up to the present time, the conventional control system has been used for the load control on nuclear steam generator, owing to the easy control algorithms and the advantage which have been proven on the nuclear power plant. However, since there are problems with stability control during low power and start-up, only a highly experienced operator can operate during those procedures. Also, a great deal of time and an expensive simulator is needed for the training of an operator. The KEPRI is developed simulator for 600MW nuclear power plant to take a test of generator load rejection, throttle valve, and turbine load control. Total load test is implemented before start up.

• Transactions of the Korean Society of Mechanical Engineers B
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• v.24 no.7
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• pp.967-975
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• 2000

Transient characteristics of a boiler and turbine system for a steam power plant are simulated. One-dimensional unsteady models are introduced for each component. An interaction between boiler and turbine and a control of the water level in the drum are taken into account. Transient responses of the system to the variations of main system variables such as fuel and air flow rate, cooling water injection rate at the attemperator, gas recirculation rate at the furnace and opening of the turbine control valve are examined. Effect of fluid inertia and tube wall thermal inertia on predicted dynamic behavior is investigated.

• Proceedings of the KIEE Conference
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• 2005.07d
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• pp.2613-2615
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• 2005

증기터빈 발전소에서 터빈제어밸브는 운전중 적절히 개도를 조절하여 보일러에서 공급되는 유량을 조절하여 터빈속도 및 발전기의 전기적 출력을 제어할 수 있도록 해준다. 이러한 터빈제어밸브는 4개로 구성되어 있으며, 운전중 최적의 발전효율을 얻기 위해 저부하에서는 4개의 제어밸브가 동일하게 조절되다가 밸브 전환 운전을 완료한 후 4개의 밸브가 주어진 특성에 따라 각기 조절되어야 할 필요성이 있다. 이때 수행되는 과도기적인 운전절차인 밸브 전환운전시 발전기 출력 등의 변화가 없어야 한다. 본 논문에서는 밸브전환 운전시 발전기 출력을 일정하게 유지하기 위하여 고압터빈 1단 압력을 궤환받아 발전기 출력을 보상하는 제어알고리듬을 제시하고 실제 발전소에 적용한 결과를 소개하고자 한다.

• Proceedings of the KIEE Conference
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• 2006.07d
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• pp.1873-1874
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• 2006

증기터빈 발전소에서 터빈제어밸브는 운전중 적절히 개도를 조절하여 보일러에서 공급되는 유량을 조절하여 터빈속도 및 발전기의 전기적 출력을 제어할 수 있도록 해준다. 이러한 터빈제어밸브는 4개로 구성되어 있으며, 운전중 최적의 발전효율을 얻기 위해 저부하에서는 4개의 제어밸브가 동일하게 조절되다가 밸브 전환운전을 완료한 후 4개의 밸브가 주어진 특성에 따라 각기 조절되어야 할 필요성이 있다. 대상 발전소에서 시행하고 있는 운전절차중 하나인 밸브전환 운전은 발전기 출력의 변화가 수반되며 이를 최소화하기 위해 고압터빈측의 1단 압력을 궤환하여 보상하는 알고리듬을 사용하고 있다. 사용중에 발전기 출력변화가 발생되어 이를 개선하기 위해 적용되는 알고리듬을 보완하여 실제 발전소 현장에 적용한 결과를 소개하고자 한다.

• KEPCO Journal on Electric Power and Energy
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• v.2 no.3
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• pp.409-413
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• 2016

The 500 MW rated steam turbine model in coal fired power plant is developed to be used for validation and verification of controller rather than for the education of operator. The valve, steam turbine, reheater and generator are modeled and integrated into the simulator. And the data from the plant heat balance diagram are used for estimation of the model parameters together with actual operating data. It is found that the outputs of model such as pressure, temperature and speed are similar to the operating ones. So, it is expected that the developed model will play a very big role in controller development.