• Proceedings of the Korea Society for Simulation Conference
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• 2000.11a
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• pp.73-77
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• 2000

현재 발전소의 시뮬레이터 교육은 교재 위주로 시행되고 있어서 발전소의 입체영상이나 가상사고 진행에 따른 동적 상태변화 등을 실감있게 교육할 수 있는 교육설비가 없다. 이러한 문제점을 보완하기 위해 가상현실 및 멀티미디어 기법을 적용하여, 발전소 전반 및 주 제어실 등을 3차원 모델로 개발하고 이를 입체영상으로 시각화하여 발전소의 복잡한 구조와 기능들을 설명하고, 운전 중 발생 가능한 다양한 사고에 대한 시나리오 선정 및 저작으로 운전원 교육시 시뮬레이터실이 아닌 강의실에서 사고현상 시뮬레이션을 가능하게 하는 시스템을 개발하기 위한 설계를 완료하였다. 본 논문에서는 3차원 CAD 데이터 구축, 가상현실 시스템 개발, 웹 환경의 교육시스템 개발, MMI 화면개발을 통한 시뮬레이터 연동 시스템 개발 등을 구현하기 위해 현재까지 설계된 컴퓨터 지원 교육훈련시스템에 대한 전반적인 내용을 제시 하고자 한다.

• Proceedings of the Korea Information Processing Society Conference
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• 2002.11a
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• pp.259-262
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• 2002

원자력 발전소는 발전소 안전과 방사선 안전등의 이유로 해서 복잡한 건물 및 기기들로 이루어져 있다. 특히 고 방사성 물질들을 함유하고 있는 1 차계통(NSSS System) 기기들은 평상 운전시 뿐 아니라 정기보수(O/H) 기간 중에도 고 방사능 지역에 위치하여 운전원의 접근이 어려운 지역이다. 본 고에서는 이러한 접근 제약성을 극복할 수 있는 교육시스템으로서 전력연구원에서 개발한 울진 표준형원전 가상현실 교육훈련 지원시스템(KSNP VRCATS)의 일환으로 가상 공간에 구현된 가상발전소(Virtual Plant)와 각종 기기 구조물, 가상 주제어실(Virtual MCR)의 개발 내용 및 특징을 기술하였다.

• Proceedings of the Korea Society for Simulation Conference
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• 2003.11a
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• pp.153-157
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• 2003

전력연구원에서는 울진 표준형원전의 시뮬레이터를 개발하였으며, 여기에는 가상 주제어실, 발전소 현상 감시, 중대사고 등 많은 클라이언트 프로그램들이 있다. 이러한 프로그램들은 시뮬레이터와 연동되어 필요한 값을 읽고 쓰는 과정이 필요하다. 그러나 현재는 해당 시뮬레이터 환경에서 개발되지 않는 외부의 응용프로그램이 이들 시뮬레이터의 값들을 엑세스하는 방법은 제공하지 않고 있다. 본 보고서에서는 이러한 문제점을 해결하기 위해 외부 프로그램들이 시뮬레이션모델의 각종 변수들을 효과적으로 엑세스하여 값을 Read/write 할 수 있는 OPC (OLE for Process Control) Server를 개발하였다. 본 프로그램은 Rockwell의 OPC Server Toolkit인 RSI OPC/DDE Server Toolkit Library를 이용하여 개발하였으며 시뮬레이터가 실행되고 있는 컴퓨터에서 실행된다. 본 보고서에서는 OPC 일반개념, 개발한 OPC Server의 소개, OPC Server의 적용결과 등을 기술하고자 한다.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.15 no.1
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• pp.1-7
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• 2019

In this paper, the regulations and technical standards related to qualification of safety grade equipment in nuclear power plants are critically reviewed with the qualification procedure in terms of structures, systems, and equipment in nuclear power plants. These facilities should be designed and constructed to protect from natural conditions or disasters and to perform their safety functions even in case of postulated accidents. Equipment Qualification is to demonstrate that the safety related equipment is designed and constructed to perform their safety functions under normal and accident conditions. It is classified into environmental qualification and seismic qualification.

• Journal of the Korean Society for Nondestructive Testing
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• v.27 no.2
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• pp.89-96
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• 2007

The bobbin probe examination is basic and the important method among other ECT techniques for the steam generator tube integrity assesment that is practiced during each plant outage. The bobbin probe is one of the essential components which consist of the whole ECT examination system, and provides us a decisive data for the evaluation of tube integrity in compliance with acceptance criteria described in specific procedures. The selection of examination probe is especially important because the quality of acquired ECT data is determined by the probe design characteristics, such as geometry and operation frequency, and has enormous effects on examination results. In this study, An optimal differential bobbin probe is designed for the steam generator tube inspection in nuclear power plants(NPPs). Based on the test results for electrical and ECT signal characteristics, the prototype bobbin probe satisfies all the criteria.

• Journal of the Korean Society for Nondestructive Testing
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• v.26 no.2
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• pp.90-98
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• 2006

Signals captured from a Combo calibration standard tube paly a crucial role in the evaluation of motorized rotating pancake coil (MRPC) probe signals from steam generator (SG) tubes in nuclear power plants (NPPs). Therefore, the Combo tube signals should be consistent and accurate. However, MRPC probe signals are very easily affected by various factors around the tubes so that they can be distorted in their amplitudes and phase angles which are the values specifically used in the evaluation. To overcome this problem, in this study, we explored possibility of simulation to be used as a practical calibration tool far the evaluation of real field signals. For this purpose, we investigated the characteristics of a MRPC probe and a Combo tube. And then using commercial software (VIC-3D) we simulated a set of calibration signals and compared to the experimental signals. From this comparison, we verified the accuracy of the simulated signals. Finally, we evaluated two defects using the simulated Combo tube signals, and the results were compared with those obtained using the actual field calibration signals.

• Journal of the Korea Institute of Information and Communication Engineering
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• v.21 no.12
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• pp.2221-2231
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• 2017

In this paper, we surveyed previous cases, network protocols (such as Wi-Fi, Zigbee, Z-wave, and WirelessHart) and propagation characteristics on the application of maintaining equipments for instrumentation and control (I&C) using wireless communication techniques inside the nuclear power plant (NPP). In addition, we compared and analyzed the difference of detailed regulations with respect to the electromagnetic interference (EMI) and radio frequency interference (RFI) in the Regulatory Guide 1.180 rev. 1 (RG. 1.180) for adopting the wireless communication techniques inside the NPP, and other regulations, such as MIL-STD 461E and IEC 61000-4, that are recognized in the KINS/RG-N03.09 (Rev. 2). Furthermore, we investigated evaluating factors about electromagnetic properties by considering indoor environments, wave scattering, shielding effectiveness, and the indoor wave attenuation model that were not included in the current electromagnetic compatibility regulation.

• Journal of Energy Engineering
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• v.23 no.3
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• pp.186-190
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• 2014

Nuclear Power Plants require the control ability of chemical condition (pH) because pH control during transient accident such as LOCA makes an able the fission product removal capability to be maintained, stress corrosion cracking of stainless steel equipment to be prevented and the production of hydrogen by aluminum and zinc to be minimized. An NPP is designed to control the pH of containment spray and sump coolant using the spray additives 30% NaOH in the event of loss of coolant accident. In this paper, the pH of sump coolant of an NPP during LOCA was analyzed and the fission products removal constant and decontamination factor were calculated according to Standard Review Plan 6.5.2 related to spray chemical conditions of pH. The calculated pH value of recirculation mode using the computer code corresponds to 8.09~9.67, which meets the chemical environment regulation requirements. The fission product removal capability caused by containment spray system is performed to provide input to radiation analysis.

• Journal of Radiation Protection and Research
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• v.28 no.3
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• pp.215-223
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• 2003

Against major release of radioactive material in nuclear power plant, Emergency Planning Zone(EPZ)s are typically established around nuclear power plants to effectively perform the public protective measures. The domestic methodology to determine the size of the EPZ is similar to that of Japan established in 1980, where calculations were based on the conservative accident source term. The objective of this study is to re-evaluate the validity of established EPZ, the area within the radius of $8{\sim}10km$ around domestic nuclear power plants, using the source terms covering full spectrum of accidents obtained from PSA study of ULJIN 3&4. To evaluate the risks of health effects, the computer code MACCS2(MELCOR Accident Consequence Code System2) was used. The result shows that the existing EPZ can reduce the probability of early fatality adequately for most of the source term categories(STCs) except for STC-14 and STC-19. In case of STC-14 and 19, the evacuation distance of 16km and 13km, respectively, are required. These distances can be reduced by improving emergency preparedness since the sensitivity studies for the public protective actions show that the magnitude of early fatality is largely affected by the time delays in notification and evacuation.

• Journal of Radiation Protection and Research
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• v.24 no.3
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• pp.131-142
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• 1999

By using the Korean demographic data and the modified relative risk projection model given in the Committee on the Biological Effect of Ionizing Radiation (BEIR) report-V under the U.S. National Academy of Science, the radiogenic excess risk in Korean population has been evaluated. On the basis of this risk, a safety goal for the safe operation of domestic nuclear power plants has been further derived in terms of personal dose. The baseline risk of death due to all causes in Korea and the trivial risk level, which the society considers safe, were estimated to be $5.2{\times}10^{-3}$ and $5.2{\times}10^{-6}$, respectively. The radiogenic excess cancer risk in Korea has been estimated to be $5.2{\times}10^{-3}$ for tie case of acute exposure to 0.1 Gy and $3.7{\times}10^{-3}$ for the case of chronic lifetime exposure to 1.0 mGy/y. On the basis of these risks estimate, the resulting safety goal for one year opeation of a reactor was 0.05 mSv, which is quite identical with the ALARA guideline prescribed by the USNRC in the Appendix I, 10CFR50.