• Proceedings of the Korea Concrete Institute Conference
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• 1996.10a
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• pp.546-550
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• 1996

The personal-computer software program named SAMS(Structural Aging Management System) was developed for the concrete structure of NPP(Nuclear Power Plant). SAMS is constituted of three part, detabase system containing various inspection data, operation program for standard input/output of the inspection data, and application program for efficient operation of database system. Using the SAMS, the field engineers can easily acquire the information about the various inspection data, repair and accidental histories of NPP structures. SAMS will contribute to the effcient maintenance of NPP structures.

• Proceedings of the KIEE Conference
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• 1993.07b
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• pp.818-820
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• 1993

In the three phase full-wave thyristor rectifier, heat radiation concentrated at a few thyristor(s), while equipment's output is normal. That is very important on the predictive maintenance or checking including replacement of parts(or modules). Therefore, this report explains the method of effective diagnosis and the reason that firing control modules have to be adjusted accuratly on each phase.

• Journal of the Korean Society of Manufacturing Technology Engineers
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• v.9 no.2
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• pp.125-137
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• 2000

In this paper we propose a new approach to the development of the automatic vision system to examine and repair the steam generator tubes at remote distance. In nuclear power plants workers are reluctant of works in steam generator because of the high radiation environment and limited working space. It is strongly recommended that the examination and maintenance works be done by an automatic system for the protection of the operator from the radiation exposure. Digital signal processors are used in implementing real time recognition and examination of steam generator tubes in the proposed vision system. Performance of proposed digital vision system is illustrated by simulation and experiment for similar steam generator moldel.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.10a
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• pp.153-158
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• 1995

All of the nuclear power plants in Korea we operating with analog instrumentation and control (I&C) equipment which are increasingly faced with frequent troubles, obsolescence and high maintenance expenses. Electrical and computer technology has improved rapidly in recent years and has been applied to other industries. So it is strongly recommended we adopt modern digital and computer technology to improve plant safety and availability. The advanced I&C system, namely, Integrated Intelligent Instrumentation and Control System (I$^3$CS) will be developed for beyond the next generation nuclear power plant. I$^3$CS consists of three major parts, the advanced compact workstation, distributed digital control and protection system including Automatic Start-up/shutdown Intelligent Control System (ASICS) and the computer-based alarm processing and operator support system, namely, Diagnosis, Response, and operator Aid Management System (DREAMS).

• Journal of the Korea Concrete Institute
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• v.11 no.5
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• pp.41-49
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• 1999

This study dealt with the applicability and quality control of the concrete using fly ash produced in combined heat power in a construction site. Firstly, chemical and physical characteristics of the fly ash produced in combined heat power plant re analysed. Also, after investigating the properties of flesh and hardened concrete through various experiments, the fly ash concrete was placed in depositing construction in Ulsan Petrochemical Service Co. This field application was focussed on the quality control system in the site as production, placing and curing of concrete. As the result of this study, the quantity of CaO in the fly ash is relatively high based on the chemical analysis. The fly ash concrete showed slumping maintenance and high viscosity properties in the optimal mixing conditions (W/B:44~45%, S/a:$45\pm$2%, W:185kg/m). And, quality control and assurance of the fly ash concrete in actual site were verified by various testing methods.

• Journal of the Korean Society of Systems Engineering
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• v.16 no.1
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• pp.84-97
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• 2020

This paper aims to develop an optimized inventory management method for safety critical Instrument and Control (I&C) components. In this regard, the paper focuses on estimating the consumption rate of I&C components using demand forecasting methods. The target component for this paper is the Foxboro SPEC-200 controller. This component was chosen because it has highest consumption rate among the safety critical I&C components in Korean OPR-1000 NPPs. Three analytical methods were chosen in order to develop the demand forecasting methods; Poisson, Generalized Linear Model (GLM) and Bootstrapping. The results show that the GLM gives better accuracy than the other analytical methods. This is because the GLM considers the maintenance level of the component by discriminating between corrective and preventive.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.16 no.1
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• pp.56-64
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• 2020

The safety related heat exchangers have been evaluated for their performance during the operation of the nuclear power plant. The evaluation program for the safety related heat exchanger was developed in 2010 and used by KHNP based on EPRI TR-10739 algorithms. The spend fuel pool heat exchanger is one of the safety related heat exchanger in the nuclear power plant and also evaluated for their performance. Recently the performance evaluation for the spend fuel pool heat exchanger was not available because of the decreased heat in the spend fuel pool due to the long term overhaul. This paper analyzes the main cause of evaluation failure in the evaluation process and suggests the criteria for the heat exchanger performance evaluation during the long term overhaul.

• Proceedings of the KIEE Conference
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• 2000.07a
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• pp.425-427
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• 2000

The purpose of this study is to find the cause of the damage to the GCB(Gas Circuit Breaker), since the GCB of the 154kV power plant at the Hap-Cheon Dam has already been damaged twice. We researched the characteristics of this class of circuit breaker and the possible causes for this type of damage to the GCB using the FTA(Fault Tree Analysis) Method. We studied the optimal maintenance method of the GCB, the stability analysis and power serge protection of Hap-Cheon Dam, and the power serge and fault list of the power transmission line to help prevent a reoccurrence of the problem.

• Proceedings of the KIEE Conference
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• 2006.07a
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• pp.151-152
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• 2006

Because power plant faults have severe effects on the power system and on mechanical maintenance of the generator, reliable protection systems are needed. In this paper, we compared and analyzed methods of the generator protection relaying system, which can defect internal faults of the generator, and surveyed the trends in generator protection using digital computing.

• Proceedings of the KIEE Conference
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• 1999.07b
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• pp.703-705
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• 1999

The Power supplies used commonly in the Nuclear, Thermal and Hydraulic Power Plant are required to test the function and reliabilities. For the better contribution of reliable operation and speedy maintenance of Power Plant, it is necessary to gather and analyze the datum, to print out the result of testing using PC and proper controllers. Various kinds of power supply shall be tested and examined automatically. By storing the test results in the Database it is possible to find out the changing of characteristics of power supplies. So it is very useful to prevent any problems that may occur in the power supplies.