• Journal of Power Electronics
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• v.16 no.4
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• pp.1612-1620
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• 2016

This paper presents the dynamic excitation control of a siphon-turbine coupled pico-hydro powered cage rotor induction generator and load matching for off-grid electricity generation. Through the proposed dual-role of the current-controlled voltage source converter (VSC), acting as static synchronous compensator and load controller, real and reactive power are dynamically controlled in a decoupled manner with a self supported DC-bus. The proposed scheme entails minimal computation for ensuring the rated (set) capacity of real power. The scheme also exhibits fault immunity for protection, thus enabling the effective handling of constant power electrical loads presented by base telecom station towers in remote locations. The performance of the system is evaluated under MATLAB/Simulink and is experimented through a developed hardware prototype. Simulation and experimental results show close conformity and validate the effectiveness of the proposed scheme.

• The Transactions of the Korean Institute of Electrical Engineers P
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• v.66 no.1
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• pp.15-20
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• 2017

In order to advance and improve the performance of domestic aged power plants, IEDs have been developed for power generation systems. For smooth installation and operation of the protection relays, a detail settings study of IED is required. This paper deals with an analysis based on PSCAD and setting investigation of IED for loss of field, reverse power protection in Small Hydro Generation System.

• Tribology and Lubricants
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• v.21 no.5
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• pp.201-208
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• 2005

This paper presents the FEM analysis on the contact behavior characteristics of mechanical face seals in a small hydro-power turbine. Especially, the axial displacement and contact normal stress between a seal ring and a seal seat of a primary sealing unit have been analyzed as functions of rotating speed of a hydro-turbine, sealing gap, water and cooling fluid temperature. Those are strongly related to a leakage of water and wear between a seal ring and a seal seat. The FEM computed results present that the rotating speed of a hydro-turbine may be kept less than 800 rpm, and the sealing gap in a primary sealing unit is restricted $0.5\~5$. The coolant temperature in which is most influential parameter to the contact behaviors of a sealing unit may be kept less than $15^{\circ}C$ for a safe operation of a sealing unit without a leakage and wear.

• Proceedings of the KIEE Conference
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• 2008.04a
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• pp.187-188
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• 2008

주기적으로 제어 성능을 평가하고, 평가 결과에 따라서 제어시스템의 제어기 상수를 최적화하거나 제어 밸브와 같은 제어기기의 문제점들을 사전에 개선하고자하는 노력이 있어왔다. 제어성능 평가방법은 제어목표 값에 대한 추종성을 평가하는 Set Point Analysis 방법을 주로 사용한다. 평가 지표는 Integral Absolute Error(IAE)와 같은 Error Integral 값과 Minimum Variance 방법이 실용적으로 사용된다. 본 논문에서는 평가 대상시스템으로 원자력발전소의 수위 제어시스템중 하나를 선정하고 Control Performance Assessment를 수행하였다. 이를 기반으로 대상 시스템의 제어모델링을 바탕으로 한 Minimum Integral Error를 만족하는 제어기 상수를 구하였으며 새로운 상수를 제어기에 설정한 후 다시 성능을 평가하였다. 평가 결과, 제어시스템의 제어 성능 평가 지표를 사용한 제어 루프의 평가와 예방 조치가 실제적으로 발전소의 안정적 운전에 유용하다는 것을 입증하였다.

• Proceedings of the KIEE Conference
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• 2008.10b
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• pp.425-426
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• 2008

발전소의 제어 시스템은 제어 기간이 길어짐에 따라 제어 기기의 운전 특성이 변화하므로 최초 설계 및 운전때의 성능과는 다른 제어 특성을 나타낸다. 따라서 주기적으로 제어 성능을 평가하고 평가 결과에 따라서 제어 기기의 성능 개선 작업과 제어 시스템의 제어기 상수 최적화 등의 작업을 통하여 제어 성능을 최적으로 유지하여 제어 목적을 달성하도록 하여야한다. 제어성능 평가기법은 제어 목표 값에 대한 추종성을 평가하는 Set Print Analysis 방법을 주로 사용한다. 평가 지표는 Integral Absolute Error(IAE)와 같은 Error Integral 값과 Minimum Variance방법이 실용적으로 사용된다. 본 논문에서는 Non-Minimum Phase 특성으로 인하여 초기 운전 모드에서 정상 운전 모듈로의 원활한 전환이 어려운 수위 제어 시스템에서 제어 전환을 위한 최적 제어기 상수를 구하기 위하여 CPA 방법을 적용하였다. 일반적으로 제어성 평가는 설정치 변화에 대한 추종성을 평가하지만 본 논문에서는 제어 전환 시의 제어성 평가를 통하여 최적의 제어 전환 상수를 구하고자 하였다. 적용 결과, CPA기법은 설정시 추종성뿐만 아니라 제어 과도에서의 제어 전환 변수의 주종성에 적용하여 제어 전환을 최적화하는데도 유용함을 확인하였다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.4 no.1
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• pp.51-58
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• 2006

Since 2002, more than 400 PWR spent nuclear fuel assemblies have been transported and stored on-site using transport casks in order to secure the storage capacity of PWR spent nuclear fuel of Kori nuclear power plant. The complete on-site transport system, which includes KN-12 transport casks, the related equipment and transport vehicles, had been developed and provided. KN-12 transport casks were designed, fabricated and licensed in accordance with Korean and IAEA's transport regulations, and the related equipment was also provided in accordance with the related regulations. The on-site transport and storage operation using two KN-12 casks and the related equipment has been conducted, and the strict Quality Control and Radiation Safety Management through the whole process has been carried out so as to achieve the required safety and reliability of the on-site transport of spent nuclear fuel.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.3 no.3
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• pp.231-236
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• 2005

HIC transport packaging to transport a high integrity container(HIC) containing dry spent resin generated from nuclear power plants is to comply with the regulatory requirements of Korea and IAEA for Type B packaging due to the high radioactivity of the content, and to maintain the structural integrity under normal and accident conditions. It must withstand 9 m free drop impact onto an unyielding surface and 1 m drop impact onto a mild steel bar in a position causing maximum damage. For the conceptual design of a cylindrical HIC transport package, three dimensional dynamic structural analysis to ensure that the integrity of the package is maintained under all credible loads for 9 m free drop and 1 m puncture conditions were carried out using ABAQUS code.

• Journal of the Korean Ceramic Society
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• v.40 no.10
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• pp.936-942
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• 2003

In order to develop glass formulations for vitrifying Low-and Intermediate-Level radioactive Wastes (LILW) from nuclear power plants of Korea Hydro & Nuclear Power (KHNP) Co., Ltd., promising glass formulations were selected based on glass property model predictions for viscosity, electrical conductivity and leach resistance. Laboratory measurements were conducted to verify the model predictions. Based on the results, the models for electrical conductivity, US DOE 7-day Product Consistency Test (PCT) elemental release, and pH of PCT leachate are accurate for the LILW glass formulations. However, the model for viscosity was able to provide only qualitative results. A leachate conductivity test was conducted on several samples to estimate glass leach resistance. Test results from the leachate conductivity test were useful for comparison before PCT elemental release results were available. A glass formulation K11A meets all the KHNP glass property constraints, and use of this glass formulation on the pilot scale is recommended. Glass formulations K12A, K12B, and K12E meet nearly all of the processing constraints and may be suitable for additional testing. Based on the comparison between the measured and predicted glass properties, existing glass property models may be used to assist with the LILW glass formulation development.

• Nuclear Engineering and Technology
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• v.46 no.6
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• pp.869-874
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• 2014

It was discovered in a Korean PWR that an extensive number of very short and shallow cracks in the SG tubes were undetectable by eddy current in-service-inspection because of the masking effect of sludge deposits. Axial stress corrosion cracks at the outside diameter of the steam generator tubes near the line contacts with the tube support plates are the major concern among the six identical Korean nuclear power plants having CE-type steam generators with Alloy 600 high temperature mill annealed tubes, HU3&4 and HB3~6. The tubes in HB3&4 have a less susceptible microstructure so that the onset of ODSCC was substantially delayed compared to HU3&4 whose tubes are most susceptible to ODSCC among the six units. The numbers of cracks detected by the eddy current inspection jumped drastically after the steam generators of HB4 were chemically cleaned. The purpose of the chemical cleaning was to mitigate stress corrosion cracking by removing the heavy sludge deposit, since a corrosive environment is formed in the occluded region under the sludge deposit. SGCC also enhances the detection capability of the eddy current inspection at the same time. Measurement of the size of each crack using the motorized rotating pancake coil probe indicated that the cracks in HB4 were shorter and substantially shallower than the cracks in HU3&4. It is believed that the cracks were shorter and shallower because the microstructure of the tubes in HB4 is less susceptible to ODSCC. It was readily understood from the size distribution of the cracks and the quantitative information available on the probability of detection that most cracks in HB4 had been undetected until the steam generators were chemically cleaned.

• Proceedings of the Korea Water Resources Association Conference
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• 2005.09b
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• pp.1264-1265
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• 2005